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F1-RC-1056.2 (F1.20.21)

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WORKING MATERIAL

Improved production and utilization of short pulsed, cold at low-medium energy sources nd Report of the 2 Research Co-ordination Meeting

Kuala Lumpur, Malaysia

2 – 4 July 2009

Reproduced by the IAEA Vienna, Austria, 2009

NOTE The material reproduced here has been supplied by the authors and has not been edited by the IAEA. The views expressed remain the responsibility of the named authors and do not necessarily reflect those of the government(s) of the designating Member State(s). In particular, neither the IAEA nor any other organization or body sponsoring the meeting can be held responsible for this material.

Contents

1. FOREWORD...... 3

2. EXECUTIVE SUMMARY ...... 3 2.1. Small angle (SANS) development...... 3 2.2. Moderator Development...... 5 2.3. Energy-dispersive transmission measurements ...... 7 2.4. Recommendations to Participants ...... 8 2.5. Recommendations to IAEA...... 9 2.6. Additional recommendations coming from the second RCM:...... 10

3. PURPOSE OF THE MEETING ...... 10

4. BACKGROUND SITUATION ANALYSIS...... 10

5. OVERALL OBJECTIVE ...... 11

6. SPECIFIC RESEARCH OBJECTIVES...... 12

7. EXPECTED RESEARCH OUTPUTS ...... 12

8. ACTION PLAN (ACTIVITIES) ...... 12

9. UPDATED WORKPLANS FOR THE PROJECTS PRESENTED AT THE MEETING ...... 13 9.1. Development of mini focusing small angle neutron scattering instruments (Japan) ...... 13 9.2. Development and optimization of a curved wide wavelength band monochromator based on strongly cylindrically bent perfect Si-slabs in a sandwich for mini-focusing small-angle neutron scattering (mfSANS) device (Czech Republic)...... 13 9.3. Development of mini-focus SANS (Malaysia) ...... 14 9.4. SANS BATAN: Improvement in the Neutron Intensity by Focusing Optics (Indonesia)...... 15 9.5. Development of very cold moderator materials at the low energy (United States of America)...... 15 9.6. Modelling and measurement of neutronic properties of new cryogenic neutron moderators (Argentina) ...... 16 9.7. Development of pulsed cryogenic moderators at a pulsed source (Japan)...... 16 9.8. R&D of productive pelletized cold neutron moderators (Russian Federation)...... 17 9.9. Developing H 2O ice based cold moderator and multilayer based neutron optical elements for enhancing cold in reactors and accelerator based sources (India)...... 18 9.10. Development of transmission method at a pulsed source (Japan)...... 19 9.11. Bragg edge transmission analysis at a medium intensity pulsed neutron source (Argentina) ...... 20

10. LIST OF PARTICIPANTS...... 21

11. LIST OF OBSERVERS...... 22

12. AGENDA...... 23

13. ANNEXES...... 24

ANNEX I. MINI FOCUSING SMALL ANGLE NEUTRON SCATTERING (SANS) 25 I-1. Development of micro focusing small angle neutron scattering spectrometers...... 27 I-2. Development and optimization of a curved wide wavelength band monochromator based on strongly cylindrically bent perfect Si-slabs in a sandwich for minifocusing small-angle neutron scattering (mfSANS) device...... 33 I-3. Development of mini-focus SANS...... 37 I-4. SANS BATAN: Improvement the Neutron Intensity by Focusing Optics ...... 47

ANNEX II. MODERATOR DEVELOPMENT ...... 53 II-1. Development of very cold moderator materials at the low energy neutron source...... 55 II-2. Modelling and measurements of neutronic properties of new cryogenic neutron moderators ...... 61 II-3. Development of Cryogenic Moderators Using a Small Proton Accelerator .... 67 II-4. R&D of productive pelletized cold neutron moderators ...... 71 II-5. A Report on the feasibility of an ice Cold Neutron Source at Dhruva Reactor...... 77

ANNEX III. ENERGY-DISPERSIVE TRANSMISSION MEASUREMENTS...... 83 III-1. Development of high resolution transmission method...... 85 III-2. Bragg edge transmission analysis at a medium intensity pulsed neutron source...... 91

1. FOREWORD

For over 50 years research reactors have supported developments in neutron beam research, new materials, and component integrity testing, and are expected to continue to do so in the coming decades. The scientific and technological problems being addressed using neutron beams are becoming increasingly large and complex that research reactors alone will not be able to cater to all the requirements. They will need to be complemented by neutron beams from spallation neutron sources, where the extremely high peak neutron fluxes and time structure of the pulsed neutron beam opens up numerous new experimental opportunities. This CRP will initiate a number of research, development, and demonstration activities that need to be undertaken to make this technology more readily available and to a wider community by way of a future global network of low and medium energy spallation neutron sources. Through this CRP, it will be investigated how high-end technologies from the flagship neutron sources can be cost-effectively adapted to lesser powered neutron sources, while assuring best experimental conditions for users in both the developing nations and industrially developed Member States. The CRP outputs would not only benefit spallation neutron facilities, but also the existing workhorse research reactors.

The meeting was attended by ten international experts and chaired by Mr M. Furusaka. The major part of the drafting of the report was done by Mr D. V. Baxter. The IAEA officer responsible for this document is Ms F. Mulhauser of the Physics Section, Division of Physical and Chemical Sciences, Department of Nuclear Sciences and Applications.

2. EXECUTIVE SUMMARY

The meeting brought together a group of 11 scientists from eight different countries with a common interest in neutron scattering. This document provides an update on progress achieved toward the goals laid out at the first RCM in Sapporo Japan (held in June 2007) and calls out specific action items to be undertaken over the remaining period of the CRP to achieve those goals that have not already been reached. In the following sections, text from the first RCM appears in standard font, with italics used to identify comments on progress to date and action items identified during the second RCM .

The meeting focused on three specific areas in which it appears significant progress may be made through the activities of the CRP over the next three years. In each case there are a number of research thrusts that will be undertaken to maximize the impact of the CRP on the larger scientific community and the interested Member States. The three areas and research thrusts are:

2.1. Small angle neutron scattering (SANS) development

– The demonstration of a working “mini-focusing SANS” instrument provides an opportunity to have a qualitative impact on this technique in terms of both its general availability world-wide and the ease with which the SANS technique may be introduced to a new facility . o This has been largely achieved by the time of this second RCM and so no specific action items toward furthering this objective have been added here; however, extensions to this goal are identified below within the context of a revised goal.

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– There is a recognized, but as yet unfilled, need to improve the treatment of incoherent inelastic effects in SANS data analysis, and three of the participating groups will form a collaboration to make progress in this area. o The key deficiency here is the lack of suitable kernels for describing inelastic scattering at relatively low q but large angles. Limited progress has been made in this thrust over the last two years due to commitments to other projects on the part of the key personnel to be involved. o Action items to be undertaken over the remainder of the CRP :  The Argentina group will provide a room-temperature water kernel (in ACE format) to the Japanese group, who will be responsible for interfacing it to the PHIT code and developing a model TOF SANS instrument (Granada to lead on one end, Furusaka to coordinate on the other).  Baxter will provide information on the LENS SANS layout to both groups (Argentina and Japan) so that this same analysis method can be used there. Baxter will also explore the suitability of the McStas code to provide a vehicle for deploying this analysis once it becomes available. – The performance of at least three existing SANS machines will be enhanced as a result of this CRP through improved beam conditioning, advances in data acquisition, and the improvement of data reduction techniques. For two additional instruments, the possibility of including a focusing mirror will be explored. o The CRP appears to be on track toward this goal. The cold source project in India is progressing and, although it is unlikely that it will have an impact on the SANS performance within the lifetime of the CRP, it is certain to have a beneficial impact on the SANS instrument at that facility eventually, the instrument at LENS is now operating, and the Indonesian instrument is functioning and efforts toward developing a focusing lens system to extend its q-range are beginning. o There has been a useful exchange between Malaysia and Japan in which Mega Harun spent 6 months at Hokkaido University working on computer simulations of the design for improvements to the Malaysian SANS instrument. Progress on this front was hampered somewhat by uncertainties in the actual performance of the Malaysian source, however it now appears that the initial concept will lead to an instrument whose flux is less than desirable. Alternative concepts will be explored (see below). o The limitations of the initial mf-SANS concept for use with a thermal moderator have become apparent during the course of the last 18 months, and some of the action items below reflect in part an adjustment to this realization. o Action items to be undertaken over the remainder of the CRP:  Design of lens elements for the Indonesian instrument. This should be used as a vehicle to introduce a local scientist to the ray tracing codes (e.g., through a visit to NPI or Dubna to learn the MC simulation for designing and developing the lens element). A TC-sponsored visit by one of the CRP members to the Indonesian site should also be investigated. Mr Saroun from Czech Republic may be an ideal candidate for the first visit to Indonesia.  Over the next 18 months alternative concepts more suitable for development of mf-SANS style instruments on thermal sources will be

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explored and used to develop a new conceptual design for a viable SANS instrument at the Malaysian source as outlined below.  Continued improvement to the instrument background and user program at the LENS instrument will be undertaken.  A collaboration between the Russian and Malaysian groups is encouraged in order to improve the existing data handling chain associated with the Malaysian SANS instrument, as well as to improve the performance of the Be filter cryostat.

As a follow-up to the first goal above, we have identified the following new goal: – To demonstrate, from a practical point of view, the utility of the mf-SANS idea, an instrument of this type should be deployed outside of Japan over the next two years. o An initial project could be to set up a mf-SANS instrument temporarily on one of the unused beamlines on LENS (Baxter to lead; components to be shipped from the Furusaka group). o Develop a conceptual design report for deploying a mf-SANS instrument at the reactor in Malaysia. A new concept involving a focusing supermirror monochromator (FSM) will be investigated with the possibility of deploying a focussing collimator version serving as a secondary option according to the following outline:  FSM concept to be more fully developed (Mikula and Furusaka to lead).  Simulation of the FSM performance. (Mikula)  Conceptual design of the combined mf-SANS instrument (Furusaka, Basu, Aziz)  We note that the work outlined here will produce modules and knowledge that will be directly applicable to efforts for upgrading the Indonesian SANS instrument as well. o A ray tracing module for one of the standard MC codes for the mf-SANS instrument components will be developed (e.g. imperfect mirror module for PHIT, VITESS, and/or McStas). Kulikov will coordinate this for VITESS with input information to be provided by Furusaka. o Ideally, multiple simulations of a mf-SANS instrument should be performed for inter-comparison and validation of the developed modules. Participants in this will include Malaysia-Japan, Russia, and USA.

2.2. Moderator Development

– The lies at the heart of all neutrons scattering experiments, but the development of new moderator concepts has been inhibited by the lack of available computer models of candidate materials at the desired temperatures, and a significant part of the CRP activity will be devoted to the development of new models. This will include the collection of appropriate data for validating the models as well as the computational work itself. o This goal appears to be well on track, with the Argentine group taking the lead in the development of computer kernels to model the performance of various moderating materials. o Kernels developed in Argentina have already been used to optimize the design of moderators in Russia and India.

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o Collaborations between this group and the USA group, and the anticipated deployment of the cool moderator at Bariloche, will expand the range of energy over which these modules can be validated. Key needs are the lack of suitable catalogue of existing data that could be used for validation of specific kernels and in many cases lack of the data themselves. Total cross section data can provide a first-order test of new kernels, but spectral measurements from test moderators are also needed for thorough validation. o Action items to be undertaken over the remainder of the CRP:  A list identifying those materials for which we have both reasonable kernels and adequate spectral data should be produced as a first step toward providing a catalogue of evaluated neutron kernels. This will require communication among the groups from Argentina, Japan, Russia, and USA.  Members of the CRP requested kernel development on HD (~18K liquid, solid at some lower temperature?) during the second RCM. If interest in other materials develops over the next 12 months, requests should be forwarded to the Argentine group .

– New moderators will be developed for the facilities of at least three of the participating groups thereby providing a significant boost to the capabilities of those facilities. o Important design and prototyping work has been completed for the Indian cold source and over the remaining time in the CRP tests with the prototype model will be performed and used to produce safety documentation will be. o Modifications to the basic LENS moderator design have been deployed and a second moderator test bed has been constructed to facilitate experiments on new moderator concepts. This capability has already been used in experimental collaborations with major neutron facilities (ISIS, SNS). o Significant progress is also being made at the Russian facility, with a full mock up of the mesitylene ball/He gas system presently at the manufacturer. It is anticipated that the system will be ready for installation near the end of the CRP’s period of operation. o The development of a cool moderator source in Argentina is nearing completion. o Recent studies in Japan have suggested that a coupled mesitylene moderator with an optimised (roughly 1cm diameter, 4-5cm deep) re-entrant hole gives roughly the same intensity as similarly optimised re-entrant hole in a methane moderator. This is a particularly interesting development for the mf-SANS idea. o Action items to be undertaken over the remainder of the CRP:  The Argentine cool source should be deployed. Its performance measured against expectations and the results transmitted to the members of the CRP  Experimental verification of the predicted performance of the re- entrant hole mesitylene moderator should be completed.  – The optimization of designs for Target/Moderator/Reflector assemblies at small scale ADNS is expected to be different from those for larger scale spallation sources or reactor sources. One of the activities in the CRP will directly address this issue.

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o This project is on track, with simulations of the performance of a low-energy Li-target based system being completed with significant detail. o Action items to be undertaken over the remainder of the CRP:  Over the remaining time of the CRP additional simulations of a Be- target based system will be initiated.

2.3. Energy-dispersive transmission measurements

– Energy-dispersive transmission measurements can provide a wealth of important data on a wide variety of materials and it is possible to perform these measurements at relatively weak sources (indeed these measurements can often be easier at weaker sources). Development of these techniques therefore offers an opportunity for national-scale neutron sources to have significant impact on local industry, but realizing this potential will require significant development of the technique. o Two groups within the CRP (Argentina and Japan) have made significant progress in this arena. Parallel development of analysis software will facilitate the eventual validation of both. – In the case of Bragg-edge measurements, the ability to identify phase distributions and residual stress in engineering parts has been demonstrated. The CRP will optimize facilities at two small-scale sources for exploiting this technique and develop enhanced data analysis software for these experiments. An exciting outcome from the meeting was the discussion of the ability to use bent crystal monochromators to perform these experiments at small or medium-scale steady-state sources. o The first of these goals has been demonstrated at two of the participating institutions (Japan and Argentina). o The use of bent crystals to measure one edge at a time has not yet been exploited by any CRP member. At present this does not fit into the capabilities of any of the participating institutions and at this time it seems best to put this idea on hold. o Action items to be undertaken over the remainder of the CRP:  The Argentine and Japanese groups should exchange samples to provide confirmation of the performance of the two experimental systems and data analysis capabilities.  In the case of strain and texture measurements, comparison to traditional measurements and analysis should be performed as well (using facilities at ISIS, J-PARC or LANL). – Transmission experiments will also be undertaken to provide the data needed for developing new computational models of moderator materials, as discussed in point 2 above. o Both the USA and Argentina facilities have conducted experiments with this goal in mind and additional experiments are being planned for the remaining time covered by the CRP. – Action items to be undertaken over the remainder of the CRP: o Additional measurements of total cross-section of VCN-relevant materials will be carried out in Argentina and USA. Again some intercomparison should be conducted.

The participants wish to emphasise that the above activities are not independent, but that there exist valuable synergies among the various activities. For example, the improved models for

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the dynamics of hydrogenous materials needed for research on neutron moderators can also contribute to more accurate handling of inelastic scattering corrections for SANS, transmission measurements on this class of materials provide valuable data for model development, the development of bent crystal optics will enhance both SANS and transmission measurements, and enhancements of moderator performance will directly increase instrument performance for these and many other techniques.

– Several examples of these synergies have been evident over the initial 18 months of the CRP. These include the exchange of personnel between Malaysia and Japan, and the use of kernels developed in Argentina in the design of moderators in Russia and India. Many of the action items identified above for the remaining period of the CRP call for specific interactions among the participants in order to encourage additional synergistic collaborations over the remainder of the CRP. As a result of the second RCM a plan has been developed to aid the Malaysian group with the installation of a new data acquisition system for the SANS instrument in order to facilitate the transfer of data to a computer suitable for later analysis. Renewed commitments have been made to collaborative action on the improvements to SANS data analysis and several groups will work together to develop suitable computer modules for a variety of simulation applications.

– Although significant progress has been made on specific fronts at individual institutions within the CRP, collaborative work among CRP members has not yet met expectations. It is our belief that the exchange of information that took place during the second RCM, along with many of the specific action items identified above will foster increased collaborative work over the remainder of the CRP time frame.

2.4. Recommendations to Participants

Here we comment on progress regarding specific recommendations that were identified at the first RCM and comment upon actions to be taken in those cases where the recommendations have not, to date, produced the desired results.

– All participants are encouraged to exploit the SKYPE software as a mechanism to enhance inter-group communication during the course of the CRP (www.skype.com). o Most of the participants have indeed loaded this program onto their computer, but it has not yet been successfully used to enhance communication between the participants on a regular basis. o All participants with such accounts should forward their account names to Francoise to have them included with the contact information in this document. – A website should be established to facilitate data and information exchange among the participating research groups. Mr. Baxter will explore the possibility of having this hosted at Indiana University. o Baxter has been unable to get such a page setup due to restrictions on access to computer systems at his institution, but there is an IAEA site holding a static copy of the report from the first RCM.

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o The Japan group suggested that it could set up a wiki server to provide this service with relative ease and the CRP members recommended that this take place. o Francoise will provide a ‘ping’ the group to update their contributions to the page once per month. o The Argentine group is developing a web site devoted to neutron transmission experiments. Participants are encouraged to provide content and comments on the site once it is in operation. – All participants are requested to acknowledge in publications that the work was performed with the support of a Coordinated Research Project from the IAEA. o To date 5 publications have provided such acknowledgement. – The hosts should prepare items or articles for Neutron News to highlight the next RCM of the CRP, and report on the progress of this first meeting . o It is recommended that this be added as a brief description associated with the announcement of the ICNX ’09 conference in KL. (The Malaysian group will see to this). – A formal proceedings should accompany the second RCM of the CRP. o This has been shifted to the final RCM of the CRP. – The participants should work to identify sources of funding to support participation at the next RCM by young scientists from developing countries, perhaps by holding an associated workshop or school. – Participants need to identify funding to support personnel exchanges among the members of the CRP. Additional recommendations coming out of the second RCM – The collaboration between the Malaysia and Japan should be continued and expanded to include the Czech Republic and Russia as outlined above. – It is recommended that Technical Contract proposals be prepared to access IAEA funding to support exchanges of personnel within the CRP. o It was specifically suggested that this could be a useful vehicle to support the development of simulations of the focusing monochromator and focusing instruments as well as the transmission of this knowledge to Malaysia and Indonesia (Saroun).

2.5. Recommendations to IAEA

– It is strongly recommended that the next meeting be held in the first week of March 2009 at Bariloche, Argentina. The group at Bariloche has appropriate facilities for hosting the meeting, and they run an electron accelerator-driven neutron source that plays a key role in several of the CRP activities. This group also participates in two of the CRP’s three main thrust areas and has active participation by a large number of young investigators. o It was decided to exploit the opportunity presented by the hosting of the second International Conference on Neutron and X-ray scattering at Kuala Lumpur by holding the second RCM in conjunction with that conference. o It is recommended that the final meeting of the CRP be held in Bariloche to allow participating groups to see the facility there. It is further recommended that this meeting take place on 6-9 December of 2010 or 4-7 April 2011. – The agency should find a way to fund travel for people from developing countries to spend a month at some of the facilities participating in this CRP in order to enhance exchange of ideas and techniques.

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o One exchange was facilitated through external funding – The agency should consider initiating a CRP specifically devoted to identifying realistic design(s) for new small-scale ADNS that could be easily deployed in developing countries. o Other ideas for a follow-on CRP were developed during the second RCM. These include development of small Accelerator Driven Neutron Sources, developments in advanced neutron optics, or compact but brilliant Inverse Compton X-ray sources. – The agency should provide some funds to support participation at the next RCM by young scientists from developing countries. – An email should be sent from the agency to the participants reminding them to provide any updates on their progress to their multilateral collaboration .

2.6. Additional recommendations coming from the second RCM:

– The IAEA should send a copy of this document along with a description of the requirements for final reports and contributions for the final publication to all participants approximately 6 weeks prior to the next RCM . – The IAEA must distribute information on the application procedures and execution of Technical Contracts to facilitate the use of this mechanism to support CRP activities. – The Skype addresses of all CRP members who were able to sign up for the service on their office computers should be added to the participant contact information given at the back of this document.

3. PURPOSE OF THE MEETING

nd The main objectives of this 2 RCM were to: – Review the project objectives, tasks, and work plans of all participants; – Review the progress in current research activities related to the CRP; – Exchange information on the research undertaken in participating laboratories with relevance to achieving the objectives of the CRP; – Review future directions and possibilities for this CRP and beyond; – Preparation of a meeting report detailing the outcomes of this working group; – Formulate recommendations for the project participants and the IAEA

4. BACKGROUND SITUATION ANALYSIS

For over 50 years research reactors have supported developments in neutron beam research, new materials, and component integrity testing, and are expected to continue to do so in the coming decades. Many of the benefits from research reactors have to be brought into today’s technical, economic, and social realities. The demands on neutron research are increasing and new coordinated research interfacing different branches of science will be necessary. New techniques, besides using research reactors, require access to spallation neutron sources, where neutron intensity is increased by two orders of magnitude with high-power sources. However, providing a worldwide access to these techniques cannot be accomplished by the few high-energy spallation neutron sources alone. A broad network of low-medium energy facilities is needed to render accessibility, availability to a wider community, to allow the development of new techniques and application, and to train new users, operators, designers and builders. Such a network will enhance the impact of the major facilities, for many 10

emerging economies and the developing nations have a keen interest to expand opportunities in education, research, and industrial applications, using , but they do not always have sufficient resources, technology, or trained manpower to establish facilities suitable for these tasks. In order to foster the application of accelerator driven neutron sources (ADNS) in developing countries, a network of medium energy accelerator driven neutron source facilities and users is proposed to generate and strengthen international cooperation in this area.

In the IAEA-TECDOC-1439 the development opportunities for accelerator driven neutron sources were thoroughly examined, putting into evidence that the construction of a new source or significant work towards it might easily exceed the scope of IAEA-sponsored CRPs. A Technical Meeting on “Use of High Energy Accelerators for Research, Therapy, and Applications of Spallation Sources” held in Vienna in 07-09 December 2005, further identified some of the specific contributions that could be of interest for the users and owners of spallation neutron sources. The experts recommended a CRP in the light of existing boundary conditions. The scope of the CRP should cover

– Improvement of spallation source by development of cryogenic moderators – Increase of potential usage of beam lines by contributing to improve mini-focusing small angle neutron scattering – Enhance capability for strain determination by improving data extraction and evaluation from high resolution energy-dispersive transmission measurements

These efforts will lead to source improvement as well as more effective source utilization. This CRP would be focused on improvement at spallation sources with a future prospect to expand neutron techniques and applications into new areas involving users in various disciplines of research.

This CRP brings together institutions with widely different possibilities and a broad spectrum of interests. It has the prospect of producing tangible results in medium term, although in its entirety it may be a more long term effort. Novel very cold moderators would greatly enhance the performance of small and medium size facilities; whereas the development of an inexpensive, compact, and versatile small angle scattering instrument and better interpretation of transmission experiments would address needs of both research and training. Taken together developments in these areas hold promise to efficiently align neutron demand and neutron supply across sources of various strengths. The CRP will also promote optimal use of the different possibilities of developed countries and emerging economies to bear in a fruitful way with benefits for all involved parties.

The experts highlighted the importance, in particular for developing countries, of having easy and quick access to small or medium size facilities for research and applications and, probably even more important, for training purposes. They also examined several networking opportunities in different areas of interest.

5. OVERALL OBJECTIVE

To enhance the utilization possibilities of low and medium energy spallation neutron sources for research and development in neutron science and applications, by increasing neutron supply at sources and by improving optimum use of neutron techniques in interested Member States.

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6. SPECIFIC RESEARCH OBJECTIVES

– To improve neutron beam flux via development of cryogenic moderators. – To improve neutron beam resolution via study of new collimator, focusing devices, and monochromators. – To develop compact small angle neutron scattering (SANS) instruments, with mini- focusing properties, for simultaneous installation at neutron beamline. – To improve capability of strain determination through time-of-flight neutron measurements: experiment and user friendly implementation of the methodology to extract the desired information from the measured cross-sections. – To carefully consider how proposed techniques and improvement could be made available for interested Member States.

7. EXPECTED RESEARCH OUTPUTS

– Establishment of bilateral and multilateral cooperation between neutron facility centers of developing and industrially developed Member States. – Contributions for new compact SANS instruments with enhanced capabilities, which are easy to handle, repair, and maintain. Improvements include: o Focusing element o Wide wavelength band monochromator o Beam line splitter or bender to install several instruments at one beam line – Development of cryogenic moderator materials and designs, improvement of scattering kernels, and optimization of systems for small-scale ADNS. – Development, implementation, and dissemination of the methodology, data acquisition, and analysis for neutron energy-dispersive transmission experiments. – Scientific publications - IAEA Technical Documents, journal papers and institutional reports and presentations at different national and international conferences and meetings.

8. ACTION PLAN (ACTIVITIES)

1. Announcement of CRP and preliminary call for proposals (Summer 2006) 2. Contracts and agreement proposals received, evaluated and approved (October 2006) 3. Research contracts and agreements awarded (November 2006). Research contracts and agreements renewed annually thereafter. 4. Co-ordinated research of participating groups within the framework of the CRP. On- going, 2006 – 2010. st 5. Hold 1 RCM of the CRP July 2007. Formulate detailed work plan. 6. Report on the status of the work, including publications and conference reports of (joint) experiments, if applicable. nd 7. 2 RCM, mid term review. Update of work progress and work plan (Mid 2009). 8. Final RCM, final report preparation (Late 2010, early 2011) 9. Final report (2011).

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2006 2007 2008 2009 2010 2011 1 X 2 X 3 X 4 X X X X X 5 X 6 X X X 7 X 8 X X 9 X

9. UPDATED WORKPLANS FOR THE PROJECTS PRESENTED AT THE MEETING

9.1. Development of mini focusing small angle neutron scattering instruments (Japan)

Chief investigator: FURUSAKA Michihiro

Detailed work plan for the next 18 months 1. Development of a wide-wavelength band monochromator based on bent perfect silicon crystal plates. It is based on new idea. To get a very wide wavelength range with relatively small beam divergence, we need to bend crystal very strongly, and at the same time, need very large beam divergence for the incident beam that matches the angles of the lattice plane of the bent crystal. We already fabricated a new beam deflector to get very large beam divergence that matches the angular change of lattice planes. We already testing the device but need detailed study. We also found that the surface roughness of the silicon plates degraded the performance of the monochromator; therefore, we should fix the problem and would like to complete the development. 2. Fabricate a new, better quality ellipsoidal mirror to reduce small-angle background. It is already underway. 3. Develop a stable detector based on the new micro-strip technology and install one to mfSANS instrument. 4. Develop a beam branching/bending device for both pulsed neutron sources, but it might be difficult to finish in 1.5 years because of financial and manpower problems.

9.2. Development and optimization of a curved wide wavelength band monochromator based on strongly cylindrically bent perfect Si-slabs in a sandwich for mini-focusing small-angle neutron scattering (mfSANS) device (Czech Republic)

Chief investigator: MIKULA Pavol

Detailed work plan for the next 18 months 1. After clarifying the reasons of lower efficiency of the monochromator for minifocusing small-angle neutron scattering (mfSANS) device of Hokkaido University, NPI Rez will prepare new set of crystal wafers.

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2. Construction of two new horizontally focusing monochromators for KAERI Daejeon and about 10 new crystal slabs (namely Si(111) and Si(220))providing different resolution at different monochromator take-off angles. 3. Construction of complete horizontally focusing monochromator for BARC Mumbai 4. Preparation of crystal slabs for horizontally and vertically focusing monochromator for BARC Mumbai. The mechanical part will be made in BARC Mumbai. 5. Construction of horizontally focusing monochromator for Malaysian Nuclear Agency 6. Monte Carlo simulations of parameters of two instruments in KAERI Daejeon. 7. Presentation of advantageous employment of focusing elements in neutron scattering instruments on international meetings and workshops.

9.3. Development of mini-focus SANS (Malaysia)

Chief investigator: Bin MOHAMED Abdul Aziz

Detailed work plan for the next 18 months – Nanostructured Material Characterizations o Sample preparation, measurement at SANS facility in BATAN with subsequent data analyses and programming o Design of micro-focusing system, shielding components and funding applications – assistance from Hokaido University o Procurement preparation for parts/hardware/materials to be purchased and fabricated – Cooling System for Neutron Beam Conditioning (Be filter) o Implementation of heat transfer mathematical models and cryostat redesign parameters o Models discrimination and parameters estimation using Computational Fluid Dynamic (CFD) software. (To model with 3D analysis and repeat experimental testing to verify our design and simulation data.) o Purchase of hardware and related controlled components for cryostat modification – Beamline Upgrading o Flight tube positioning and alignment. o Modification of front collimator external shielding. – Monte Carlo Simulation: MCNP - Shielding Calculation o Expansion of the MCNP5 modeling to the whole SANS beam port and SANS facility. o Evaluation of computing hardware and software items to be purchased o Testing and verification of instrument characteristics and performance – Monte Carlo Simulation: McStas Beam Instrument Calculation o Evaluation of SANS existing set-up and set-up with reflection/focusing mirror o Testing and verification of instrument characteristics and performance

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9.4. SANS BATAN: Improvement in the Neutron Intensity by Focusing Optics (Indonesia)

Chief investigator: PUTRA Edy Giri R.

Detailed work plan for the next 18 months – Workshop/Training Course/On Job Training (OJT) on Monte Carlo calculation program – theory and applications, through IAEA's TC program, i.e. IAEA Expert Mission for local neutron scattering scientists (2009). The Monte Carlo calculation program for development of neutron instrument has to be exposed initially to the local scientists.

– A simulation using a Monte Carlo calculation program to calculate the theoretical intensity and profile patterns at SANS spectrometer with a various configuration (2009 – 2010) will be utilized.

– Joining either the NPI in Czech Republic or JINR in Russia for enhancing the knowledge and experience of one Indonesian neutron scattering scientist on designing and developing the new focusing lens of SANS BATAN (2010).

– Implementation of the detector monitor, pre-Amplifier and its electronics system for present count data acquisition will take place in 2010.

9.5. Development of very cold moderator materials at the low energy neutron source (United States of America)

Chief investigator: BAXTER David

Detailed work plan for the next 18 months 1. Over the next 18 months, we will continue to conduct total cross-section measurements of various materials that may be suitable for future VCN moderators. Specific examples to be explored include mesitylene, methanol, toluene, and methane (and, we hope, deuterated versions of these as well). Mixtures of these materials (and others) will also be used in an effort to develop candidate amorphous moderator materials (for which there will be additional low-energy modes, and in which damage may be less of an issue). Our goals will be to provide data to other CRP members who are also interested in scattering kernel development, and to demonstrate materials that may prove useful for application in future VCN moderators. We will also continue more quantitative assessment of the scattering kernel developed during the first year of the project. 2. In addition to this work, we will continue our collaboration with several major neutron sources exploring novel neutron moderator designs. Some of this work is directed at lowering the spectral temperature, but much is also simply concerned with increasing moderator brightness, controlling emission time distributions, and increasing our confidence in the scattering kernels that lie at the heart of the simulation codes that are used in source design. 3. We also expect to work with other members of the CRP (and others) to investigate the impact of incoherent inelastic scattering on Small Angle Neutron Scattering. In particular,

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we wish to investigate whether detailed analysis of the total cross section of a sample can provide any insight into this contribution to the SANS background.

9.6. Modelling and measurement of neutronic properties of new cryogenic neutron moderators (Argentina)

Chief investigator: GRANADA Rolando

Detailed work plan for the next 18 months 1. To produce scattering kernels for several deuterated materials of interest as cold-, very cold-, and ultra cold-neutron moderators, the list will include solid , solid d-methane, and deuterated solid aromatic hydrocarbons. 2. To generate and validate the cross section libraries for those materials over a wide range of temperatures, in a format appropriate for MCNP calculations; 3. To propose new composite deuterated materials that could give an enhanced performance in terms of long wavelength neutron production and radiolysis resilience; 4. To improve our experimental capabilities by operation of a new cold source in our pulsed facility; 5. To strengthen multilateral cooperation between groups involved in the improvement of experimental capabilities or techniques around neutron facility centers; 6. To disseminate the new knowledge and developments related to advanced cold moderators through scientific publications and presentations in national and international meetings.

9.7. Development of pulsed cryogenic moderators at a pulsed source (Japan)

Chief investigator: KIYANAGI Yoshiaki

Detailed work plan for the next 18 months 7 When we use the Li (p, n) reaction to produce neutrons, γ-rays of 14MeV or higher energy 7 may be generated by the resonance capture of protons of 411 keV by Li. The yield of 4) photons of 14MeV were roughly estimated and not yet measured. The results that we have calculated so far showed that the photons of 14MeV strongly dominate the surface photon 7 dose on the shielding components around the Li (p, n) cold neutron source. Thus we are 7 planning to measure the yield and the spectrum of the photons that are generated by the Li (p, n) reactions in a thin Li target equipped with the 3 MeV Pelletron accelerator of the Research Laboratory for Nuclear Reactors at the Tokyo Institute of Technology. However, the research fund has not been acquired. For the development of a fixed type intense neutron source for neutron scattering experiments, we will also perform R&D to look for the best materials and a configuration for 9 a coupled methane moderator system consisting of a Be target, a pre-moderator and a reflector as well as a moderator. Furthermore, a mesitylene moderator system will be also studied since it is much preferable than the methane one in the facilities having a serious safety regulation, and new materials, if they exist, will be also studied. From this research we

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9 will design the best moderator system for the combination of the Be (p, n) reactions with the small proton linac. We have planed the following items but the budget for these researches is partly confirmed and we need other sources for the researches.

1. Simulation Calculation to Obtain the Optimal System of Coupled Methane Moderators. We will study a slab shape moderator to obtain optimal condition of the moderator system to get the highest performance. Combination of moderator material, premoderator and reflector is studied in more detail. The configuration to get beam lines as many as possible is an important issue to accelerate the neutron scattering experiments. Therefore, we also examine the method to get many beam lines at one neutron moderator system. Furthermore, we will study a coaxial cylindrical moderator with an inside pre-moderator and an outside methane moderator to increase the number of neutron beam ports around the moderator and improve the efficiency for use of slow neutrons. For the coupled methane moderator system equipped with the 9Be target, coupling effects of reflector materials (, lead and so on) and pre-moderator materials (water, mesitylene and so on) on the neutron intensity will be studied in detail. 2. Same Simulation Calculation for Mesitylene Moderators 3. Designing the Optimal Moderator System of a Coaxial Cylindrical Type Moderator

9.8. R&D of productive pelletized cold neutron moderators (Russian Federation)

Chief Investigator: SHABALIN Evgeny represented by KULIKOV Sergey

Detailed work plan for the next 18 months July 2009 – December 2009 : Completion of construction of the full scale model of the technological system of the cryogenic moderator assigned to make testing of the main parameters of the moderator technology: - manufacturing of mechanical parts of the model; - elaboration of control and detection equipment, and system of collection and data presentation; - adopting the helium cooler to the model; - installation of the model; - elaboration of an experimental programme.

January 2009 – March 2010: Execution of the experimental programme at the full scale model of the technological system of the IBR-2M cryogenic moderator: - Measurement of the technical characteristics of the helium blower; - Measurement of heat load onto the cryogenic pipelines; - Measurement of distribution of delivery time and velocity of mesitylene beads at the given parts of the conveying pipe and the moderator chamber at various conveying gas flow rate; processing of the experimental data and analysis, choice of acceptable gas flow rate providing integrity of the beads.

March 2010 – April 2010: Proceeding of execution of the experimental programme: 17

pneumoconveying of mesithylene balls one by one at various input frequency – estimation of acceptable frequency of input balls into conveying pipe providing their uninterrupted charging into the chamber.

May 2010 – October 2010: Elaboration of an apparatus for neutron radiography of the cold moderator at the IBR-2M.

Nov. 2010 – Dec. 2010: Preparation of a final report

9.9. Developing H 2O ice based cold moderator and multilayer based neutron optical elements for enhancing cold neutron flux in reactors and accelerator based sources (India)

Chief investigator: BASU Saibal

Detailed work plan for the next 18 months 1. Complete Monte Carlo simulation process for obtaining the optimized geometry of the moderator pot: As described earlier, we have undertaken optimization of the moderator geometry for best possible output of cold neutrons from the ice moderator. We have already got the preliminary results for the ice cold source located at beam hole CS 3003 in Dhruva. This is a dedicated beam hole for the cold source. The input spectrum for the cold source is known for this location and that has been used in the Monte Carlo program. We are optimizing the thickness of the moderator at the abovementioned location for an ice temperature of 100 K. 2. Complete the engineering design of the moderator pot using finite element techniques for simulating the ice formation process, so that no water can remain trapped in the moderator pot at the time of ice formation. Otherwise there will be large stress developed in the moderator pot, every time ice is formed and the moderator pot will fail eventually. 3. Prepare a complete flow diagram (based on the experience of Mock Up test) and a fail-safe control logic for operation of the cold source. 4. Prepare a complete safety report for the installation of the cold source. This safety report will contain design of various components, based on our tests and simulation results. The safety report will be submitted for evaluation and needs to be cleared before we attempt installation of the cold source in the reactor. 5. Design the shielding for the specified beam hole and get it cleared by safety committee and then fabricate the same.

6. Procure and install LN 2 dewars in the vicinity of the reactor hall of Dhruva. Arrange laying of cryogenic lines to the beam hole mouth for cold source. 7. Assemble the components of the in-pile assembly inside the vacuum jacket and test.

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9.10. Development of transmission method at a pulsed source (Japan)

Chief investigator: KIYANAGI Yoshiaki

Detailed work plan for the next 18 months 1. Model experiments to verify the reliability of the transmission method We are developing a new data analysis code for the transmission method to get the information of crystal structure and texture. To verify the validity of the code, experiments of in-situ strain measurements will be performed by using both methods of the transmission and the diffraction.

2. Simulation for studying the optimal condition of the experimental setup for the transmission method The transmission spectra are affected by the multiple scattering and sometimes the small angle scattering. To assess the effect of the multiple scattering and beam divergence is important to perform the data analysis for the precise information on preferred orientation, strain distribution and so on. We are developing a simulation code that can simulate the inelastic and the in the forward direction. We will complete the code development and perform the calculations to know the multiple-scattering effect including the beam divergence on the transmission spectrum and finally get the optimal condition of the experimental setup.

3. Detailed observation on a welded sample We will investigate in more detail the texture and the residual strain in the steel welding material. Welding material consists of parent material, welded place and heat affected zone (HAZ). The texture can have a marked effect on the overall shape of the Bragg edge profiles recorded for each hkl reflection. From the change of shape of Bragg edge profile, welded material may be divided into parent material, welded place and HAZ. In order to understand the detailed mechanism of a fatigue failure of welding material, we will try to specify the positions of parent material, welded place and HAZ and determine the residual strain quantitatively at different texture by one measurement.

4. Effect of the crystalline size on the transmission cross section Grain size affects the total cross section of the crystalline materials. We have already measured transmission spectra of two SS samples having different grain sizes. It was observed that the transmission cross section of the large grain size sample was smaller than that of the smaller sample. However, the method to evaluate the grain size effect has not been accomplished. We will proceed with a study on the grain size effect.

5. Experiments on practical materials In order to evaluate the effectiveness of high resolution transmission measurements, some experiments on the practical materials will be performed.

6. Detector development We are now developing a GEM detector with KEK and application of a color imaging intensifier (Color I.I.) to the time-of-flight method with Toshiba co. We will improve the detection efficiency of the GEM detector and apply Color I.I. for the precise measurement of time-of-flight spectroscopy.

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9.11. Bragg edge transmission analysis at a medium intensity pulsed neutron source (Argentina)

Chief investigator: SANTISTEBAN Javier

Detailed work plan for the next 18 months 1. Implementation of Bragg edge transmission beamline at the Bariloche LINAC a. Commissioning of the recently-built cold moderator and associated cryogenic device. b. Installation of a new neutron beam monitor for this beamline. c. Installation of a transmission detection bank optimized for studying small samples. d. Implementation of Nexus-compatible file formats within the data acquisition software (see section below). 2. Development of a Bragg edge computer code a. Definition of input/output routines using the Nexus format b. Definition of a “TOF transmission” instrument within the Nexus format. c. Creation of a Matlab library for single-Bragg edge fitting analysis. d. Creation of a Matlab library for the calculation of total cross section of textured materials. e. Publication of the software via a dedicated webpage

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10. LIST OF PARTICIPANTS

Mr José Rolando Granada Mr Michihiro Furusaka Comisión Nacional de Energía Atómica Hokkaido University; Graduate School of (CNEA) Engineering Centro Atómico Bariloche; Division Kita-13, Nishi-8, Kita-ku Neutrones y Reactores Sapporo 060-8628 Av. Bustillo km 9,500 Japan 8400 San Carlos de Bariloche Email: [email protected] Argentina Tel: +81 11 706-6677 Email: [email protected] Fax: +81 11 706-6677 Tel: +54 2944 445223 Skype: michifurusaka Fax: +54 2944 445299 Skype: rolando.granada Mr Yoshiaki Kiyanagi Hokkaido University; Graduate School of Mr Pavol Mikula Engineering Academy of Sciences of the Czech Republic Kita-13, Nishi-8, Kita-ku (ASCR) Sapporo 060-8628 Nuclear Physics Institute v. v. i.; Japan Department of Neutron Physics Email: [email protected] Husinec-Rez, 130 Tel: +81 11 706-6650 250 68 Rez Fax: +81 11 706-7368 Czech Republic Skype: Email: [email protected] Tel: +420 2 6617 3553 Mr Hiraga Fujio Fax: +420 2 2094 0141 Hokkaido University; Graduate School of Skype: pavol.mikula1 Engineering Kita-13, Nishi-8 Mr Saibal Basu Kita-ku Solid State Physics Division Sapporo 060-8628 Bhabha Atomic Research Centre (BARC) Japan Trombay Email: [email protected] Mumbai, Maharashtra 400 085 Tel: +81 11 706- 6652 India Fax: +81 11 706- 6652 Email: [email protected] Skype: Tel: +91 22 25594588 Fax: +91 22 25505151 Mr Abdul Aziz Bin Mohamed Skype: Ministry of Science, Technology and Innovation Mr Edy Giri Putra Malaysia Nuclear Agency National Nuclear Energy Agency (BATAN) Division of Industrial Technology; Materials Gedung 40 kawasan Technology Section Puspiptek Serpong Kompleks MINT, Bangi Tangerang, Jawa Barat 15314 43000 Kajang, Selangor Indonesia Malaysia Email: [email protected] Email: [email protected] Tel: +62 21 7566727 Tel: +60 3 89250510 Fax: +62 21 7560926 Fax: +60 3 89250907 Skype: not yet available Skype:

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Mr Sergey Kulikov Email: [email protected] Joint Institute for Nuclear Research (JINR) Tel: +1 812 855 0932 ul. Joliot-Curie, 6 Fax: +1 812 855 5533 141980 Dubna, Moskovskaya Oblast Skype: david.v.baxter Russian Federation Email: [email protected] Ms Françoise Mulhauser Tel: +7 49621 65915 Department of Nuclear Sciences and Fax: +7 49621 65253 Applications Skype: s_kulikov2002 International Atomic Energy Agency Wagramer Strasse 5 Mr David Baxter A-1400 Vienna Department of Physics Austria Swain Hall W 117 Email: [email protected] rd 727 E. 3 St. Tel: +43 12600 21753 Indiana University Fax: +43 126007 Bloomington, IN 47405-7105 Skype: myfanfan9 United States of America

11. LIST OF OBSERVERS

Mr Anwar Abdul Rahman Malaysia Nuclear Agency Ministry of Science, Technology and Kompleks MINT, Bangi Innovation 43000 Kajang, Selangor Malaysia Nuclear Agency Malaysia Kompleks MINT, Bangi Email: [email protected] 43000 Kajang, Selangor Malaysia Ms Faridah Md Idris Email: [email protected] Ministry of Science, Technology and Innovation Mr Azraf Azman Malaysia Nuclear Agency Ministry of Science, Technology and Kompleks MINT, Bangi Innovation 43000 Kajang, Selangor Malaysia Nuclear Agency Malaysia Kompleks MINT, Bangi Email: 43000 Kajang, Selangor [email protected] Malaysia Email: [email protected]

Mr Wan Khalil Wan Ahmad Ministry of Science, Technology and Innovation Malaysia Nuclear Agency Kompleks MINT, Bangi 43000 Kajang, Selangor Malaysia Email: [email protected]

Mr Mohd rizal Mamat Ibrahim Ministry of Science, Technology and Innovation

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12. AGENDA

Thursday, July 2, 2009

09:00 – 09:45 Opening of the Meeting Welcoming Remarks Announcements Election of Chairperson and Rapporteur Discussion of the Agenda Approval of the Agenda Introduction of the participants 09:45 – 10:00 Status Report on the CRP Administrative arrangements for the meeting Introduction to the IAEA Co-ordinated Research Projects Ms. F. Mulhauser, IAEA 10:00 – 10:15 Opening by DDG 10:15 – 10:45 Coffee break 10:45 – 13:00 Progress Report (4x30minutes) and Discussions Session: Mini focusing SANS Japan (Mr Furusaka) Czech Republic (Mr Mikula) Malaysia (Mr Bin Mohamed) Indonesia (Mr Putra) 13:00 – 14:00 Lunch Break, IAEA Hospitality Event 14:00 – 17:00 Presentations (5x30minutes) and Discussions Session: Neutron sources USA (Mr Baxter) Japan (Mr Hiraga) Russian Federation (Mr Kulikov) India (Mr Basu) Argentina (Mr Granada)

Friday, July 3, 2009

08:30 – 13:00 Visit of Malaysian Nuclear and Centre 13:00 – 14:30 Lunch break 14:30 – 15:00 Presentations (2x30minutes) and Discussions Session: Transmission Measurements Argentina (Mr Granada) Japan (Mr Kiyanagi) 15:00 – 15:30 Coffee break 15:30 – 18:30 Summary of Progress reports versus Research objectives and expected outputs of the CRP: Discussion 20:00 – 22:00 Nuclear Malaysia Hospitality Event

Saturday, July 4, 2009

09.00 – 14:00 Discussions, drafting of the meeting report and closing of meeting

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13. ANNEXES

Individual progress reports for each project are given in this section.

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ANNEX I. MINI FOCUSING SMALL ANGLE NEUTRON SCATTERING (SANS)

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I-1. Development of micro focusing small angle neutron scattering spectrometers

Main collaborators: M. Furusaka, F. Fumiyuki, A. Homma, Y. Kiyanagi, T. Kamiyama, F. Hiraga Division of Quantum Science and Engineering, Graduate School of Engineering, Hokkaido University, Kita-13 Nishi-8, Kita-ku, Sapporo, 060-8628, Japan Fax: +81-11-607-6677, E-mail: [email protected]

Other collaborators: K. Kamada, Y. Sasaki, K. Koyama, Y. Okusawa, N. Ishikawa (Hokkaido Univ.) P. Mikula (INR, Czeck Republic), H. Takahashi (Univ. Tokyo, Japan), K Hirota, Y. Otake, K. Ikeda (RIKEN, JAPAN) S. Naito, H. M. Shimizu, S. Ikeda, S. Satoh (KENS, Japan) M. Sugiyama (KUR, Japan), T. Sato (KUR, Japan, currently at Hokkaido Univ.), H. Yoshizawa, M. Shibayama, H. Endoh, Y. Kawamura, T. Asami (ISSP Univ. Tokyo)

I-1.1. Short summary of work done in our group.

Constructed two prototypes of "micro-focusing", now changed to "mini-focusing" SANS (mfSANS) instrument, one at the low-power pulsed-neutron source based on 45 MeV electron linac at Hokkaido University, and the other at the cold guide tube of JRR-3 reactor at JAEA (Japan Atomic Energy Agency). They are still in an infant stage, but successfully obtained several SANS data. Analysis program development is also underway.

To realize the instruments, several neutron device developments were necessary.

1. We fabricated a wide-wavelength band monochromator based on bent perfect silicone crystal made of a stack of 30 thin plates. We found significant intensity loss, maybe due to surface roughness of the crystal plates. Detailed analysis is underway.

2. We made two ellipsoidal mirrors, one with nickel and the other with 2.5 Q c supermirror coating. The latter has sufficient quality for a focusing SANS instrument, but we are developing a new mirror made of different material (float glass instead of borated glass) with much better surface finish.

3. We are currently using a zinc sulfide (lithium) scintillation counter based on a resistive- wire type photo-multiplier tube. A high-resolution detector that has inherently better performance based on a new type of micro-strip technology has been tested and the prototype is working quite nicely.

4. We are trying to development a beam branching/bending device for both pulsed neutron sources. First basic test experiment has been carried out, but it is still in a very preliminary stage.

I-1.2. Scientific scope of your project under the CRP

Research activities using neutron scattering techniques are strongly hampered by its limited machine-time availability. We need very large facilities, either a research reactor or an accelerator driven neutron source, and the number of such facilities all over the world is rather limited. Also true is the number of instruments at such facilities. As a result, getting machine

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time of one of such instruments is also severely limited; often they are oversubscribed by a factor of three or more.

In case of X-ray, there are a lot of laboratory based X-ray instruments all over the place. Instruments are commercially available; researchers can test their ideas or new samples without writing a proposal; many researchers know how to analyze data. If you need a more powerful instrument, synchrotron radiation facilities are there.

One way of overcoming this situation around neutron scattering technique, especially for SANS instrument, would be to develop a compact unit instrument that can be installed many on a beamline. The unit should be of low cost and can also be installed at low power accelerator based neutron sources. The answer to this is the mfSANS instrument. By using a neutron-focusing technique, like an ellipsoidal mirror we are developing, we can make a very compact SANS instrument. Current ones are 2.5 and 4m in total lengths.

We have to develop many devices, such as high intensity monochromator, beam branching device, high quality focusing mirror, and detector with high-resolution/high-count-rate /high- detecting efficiency. Also important is to develop easy to use software.

I-1.3. Detailed work plan for the next 18 months

1. Development of a wide-wavelength band monochromator based on bent perfect silicone crystal plates. It is based on new idea. To get a very wide wavelength range with relatively small beam divergence, we need to bend crystal very strongly, and at the same time, need very large beam divergence for the incident beam that matches the angles of the lattice plane of the bent crystal. We already fabricated a new beam deflector to get very large beam divergence that matches the angular change of lattice planes. We already testing the device but need detailed study. We also found that the surface roughness of the silicone plates degraded the performance of the monochromator; therefore, we should fix the problem and would like to complete the development.

2. Fabricate a new, better quality ellipsoidal mirror to reduce small-angle background. It is already underway.

3. Develop a stable detector based on the new micro-strip technology and install one to mfSANS instrument.

4. Develop a beam branching/bending device for both pulsed neutron sources, but it might be difficult to finish in 1.5 years because of financial and manpower problems.

I-1.4. The results obtained till now under the CRP

The first prototype mini-focusing small-angle neutron scattering (mfSANS) instrument was tested at the pulsed cold neutron facility based on a 45 MeV electron linac at Hokkaido University. The moderator was a solid methane moderator at about 17K together with a polyethylene premoderator at an ambient temperature therefore the spectrum was a combination of cold and thermal ones.

An ellipsoidal mirror of 900 mm in length made of three pieces was fabricated by the joint- venture company J-NOP as a prototype. The long radius of ellipsoid is 2 m, and the length between focal points 4 m. The mirror was made of 3 pieces of borated glass plates and the

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surface was coated by Ni; the short radius is 20 mm and the height of the ellipsoidal part of the mirror was 20 mm at the center.

At one of the focal points, a plate with an aperture in between 1 and 10 mm in diameter was placed, and at the other focal point a detector made of zinc-sulfide with lithium neutron converter was place. Sample was placed just after the mirror, and the scattering path length to detector was about 1.4 m. We also placed a shielding plate to eliminate the neutrons that went through the upstream aperture, but did not reflected by the mirror and directly hit the detector.

Figure 1: Preliminary result of small-angle scattering in a piece of bovine thighbone. Red squares showed data obtained by mfSANS installed at Hokkaido University and blue and green ones by the one at JRR-3. Because this was a prototype, some part of the mirror surface was not smooth enough. We scanned the mirror surface with a cadmium pinhole placed just in front of the mirror, and check the focused beam on the detector whether it had a good shape. Only parts of the mirror that showed good direct beam shape by focusing were used.

When an upstream aperture of 5 mm in diameter was used, we obtained about the same direct beam size in FWHM. With a 1 mm diameter aperture, we obtained about 1.5 mm beam size in FWHM but with slightly elongated shape in longitudinal direction.

We measured several samples by the machine; one was iron or nickel powder in 20 nm in diameter, a micro-separated block co-polymer sample and water as standard samples and other ones like three pieces of bovine thighbone with different characteristics. We are developing an analysis program using Walfram made Mathematica program, but it is still in a preliminary stage.

Preliminary data taken by this machine and the one at JRR-3 were shown in Fig. 1. The sample was a piece of bovine thighbone. It was shown by the data that Qmin of 0.002 to 0.003 A-1 was obtained by this instrument. Qmax was only about 0.07 A-1 because of the detector size; it can be extended by placing higher angle detector like an array of linear position-sensitive detectors (LPSD) that is shown below. The larger Q-ranges were covered by the mfSANS instrument installed at JRR-3 with different aperture sizes.

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Figure 3: Ellipsoidal mirror placed inside of a Figure 2: mfSANS instrument installed at JRR-3. vacuum chamber. A second prototype mfSANS instrument has been installed at the cold neutron guide beamline, C1-3, at JRR-3 research reactor of Japan Atomic Energy Agency (JAEA)

In this case, an ellipsoid neutron mirror with supermirror coating of 2.5 Q c was used. The distance between the focal points was 2.5 m, considerably shorter than the one at Hokkaido University. The length of the mirror was also 900mm, made of three pieces.

Figure 4: The zinc-sulfide scintillation detector shown at the center and an array of linear position sensitive detectors of the mfSANS instrument at JRR-3. The instrument was installed not at horizontal plane, but tilted by 45 degrees toward ceiling from the horizontal line. A photograph of the instrument is shown in Fig. 2. The focusing mirror was installed in a vacuum chamber shown at the center of the photograph. A monochromator and a cadmium aperture were place in the shielding box shown at the bottom, the detector at the top part of the photograph. In Fig. 3 was shown the ellipsoidal mirror installed in the vacuum chamber. The LPSD was installed just in front of the zinc-sulfide scintillation detector as shown in Fig. 4. We successfully obtained about 2.5 mm FWHM focused beam at the detector position using a 2 mm aperture at one of the two focal points of the focusing mirror. We obtained SANS data from standard samples, such as Ni powder of 20 nm in diameter and micro-separated block-copolymer DI33, and preliminary results are shown in Fig. 5 and 6, respectively.

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Figure 5: Preliminary data; Small-angle scattering in nickel powder standard sample of 20 Figure 6: Small-angle scattering in a micro- nm in diameter. separated block co-polymer. -1 -1 The accessible Q-range for the instrument at JRR-3 was about 0.005 A to 0.02 A . They shifted to higher Q ranges because the distance between the sample and detector was about 760 mm, about half of the one of the instrument at Hokkaido University. Q max becomes -1 significantly larger, 0.5 A if we combine the LPSD detector bank data. We still have a small-angle background problem due to the surface roughness of the ellipsoidal mirror; we had to give up the final finish because of a failure of the grinding machine. It should be noted that even with such a mirror, we obtained reasonable small-angle scattering data shown above. We are fabricating a new mirror with much better surface finish now with float glass substrate instead of borated glass one, because the former is more ductile.

Figure 7: Schematic diagram of a neutron-beam deflector bender complex. A bent prefect silicone monochromator was placed at a monochromator shielding of Ultra- Low-angle Scattering instrument (ULS), just down-stream of the monochromator of ULS. The monochromator is made of a stack of 30 silicone crystal plates of 0.5 mm in thickness, 120 mm in length and 20 mm in width, placed at the fully asymmetric diffraction geometry. The bent radius was about 2m and 5.8 A neutrons were extracted by using a (111) lattice plane with 2 θ of 135 degree.

Unfortunately, the performance of the monochromator for mfSANS at JRR-3 is very poor at this moment. We fabricated and testing a better monochromator as shown in Fig. 7. It is based on bent-perfect-silicone crystal slabs with a beam divergence enhancement device consisting of many supermirrors at an upstream position. Design goal is to obtain ∆λ/λ of more than 1%.

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I-2. Development and optimization of a curved wide wavelength band monochromator based on strongly cylindrically bent perfect Si-slabs in a sandwich for minifocusing small-angle neutron scattering (mfSANS) device

Chief Scientific Investigator : RNDr. Pavol Mikula DrSc.

Nuclear Physics Institute v.v.i., AS CR, 25068 Rez, Czech Republic

Fax: +420-220940141, E-mail: [email protected]

I-2.1. Short summary of work performed in the NPI during the last 3-4 years which is related to the contract

Neutron diffraction group of Neutron Physics Department of NPI Řež has a high credit in neutron scattering community and keeps world priority in application of Bragg diffraction optics based on cylindrically bent perfect crystals in neutron diffractometry and spectrometry.

In the last 4 years the activity has been followed in two ways: An employment of already developed focusing devices based on cylindrically bent perfect crystals in high resolution neutron diffractometers and spectrometers and testing of new designs of high and ultrahigh resolution focusing monochromators/analyzers [1-12]. First, in 2007 we have provided know- how and two focusing devices for double crystal SANS diffractometer for Demokritos Institute in Athens. Then, similarly we have provided two horizontally and vertically focusing devices to HMI Berlin, where after an installation the figure of merit of neutron diffractometer has increased by a factor of 12. Also in 2006 we have provided focusing monochromators to BARC Mumbai and in 2005 and in 2008 to KAERI Daejeon and JINR Dubna. However, NPI has been engaged to a large extent in Monte Carlo simulations of neutron scattering devices employing neutron optics elements. Such MC simulations have been done namely for HMI Berlin (2006), JINR Dubna (2007), NECSA South Africa (2008) and CIAE Beijing (2008). It should be pointed out that NPI is widely recognized (at the European level) RESTRAX software package for estimation of characteristic properties of designed performance of neutron scattering devices and their optimization. The unique of the RESTRAX package for neutron ray tracing consists in its possibility of implementing the neutron optical elements (e.g. curved crystals, flat or curved mirrors and supermirrors, any type of collimators etc.)

I-2.2. Scientific scope of the project under the CRP

The main task related directly to CRP project was participation at the development of focusing monochromator for micro(mini)-focusing SANS device designed by Hokkaido University. The idea of the micro(mini)-focusing SANS device proposed by the Department of Mechanical Intelligence Engineering, Hokkaido University supposes to employ a cylindrically bent perfect (sandwich) monochromator and two curved focusing supermirrors. It represents an inexpensive and compact SANS performance permitting measurements in a large scale momentum transfer which can be installed at a cold neutron source. According to the research plan introduced in the proposal of the CRP research contract, we have prepared several sets of crystal slabs for the CRP partner Hokkaido University.

– First, individual silicon ingots were bought and oriented by using X-ray diffractometer for a consequential cutting.

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– Two sets (2x30) of the perfect silicon crystal slabs of a special cut with the lattice planes (111) at the angle 67.5 deg have been prepared. The dimensions of the slabs are: 3 120x20x0.5 mm (length x width x thickness). Therefore, such a cut of the crystal slabs permits us to use the bent focusing monochromator in the so called fully asymmetric diffraction geometry when employing it just at the Bragg angle of 67.5 deg. The monochromator in the form of sandwich containing these slabs will be installed at the C1-3 position of the reactor JRRR-3 in Tokai for a prototype of the newly designed mfSANS instrument. The thickness of the slabs is 0.5 mm and all were polished to remove a slightly damaged surface brought about by cutting wires. One set of the crystal slabs will be as a spare one.

– Two sets (1x30 and 1x40) of the crystal slabs of the same orientation which will be used for mechanical tests (minimum curvature, optimum number of slabs in the sandwich) have been prepared.

– We have carried out calculations related to reflectivity parameters of a strongly curved sandwich type monochromator consisting of thin silicon crystal slabs.

– During my stay in Hokkaido University (July 15 – July 25, 2007) a demonstration of manipulation with the sandwich type curved monochromator was carried out.

First mock-up test experiments of a time-of –flight type mfSANS was already carried out at a small pulsed cold-neutron source at Hokkaido University and then in JAERI Tokai [13,14]. First results were presented at the ICANS-18 conference in Dongguan City, (China) April 26- 29, 2007 and on the related First CRP Coordination Meeting held in Sapporo, July 23-25, 2007. Recent results were presented in the contribution of prof. M. Furusaka at the ICNX 2009 conference in Kuala Lumpur (June 29 – July 1, 2009) and also at the CRP meeting in Kuala Lumpur (July 2-4, 2009).

Thanks to the CRP project and meetings, new contacts of mutual collaborations have been also established. Within these collaborations our know-how in the Bragg diffraction optics can be provided to other laboratories, which are interested in employment of focusing devices in their neutron scattering devices (see the next chapter).

I-2.3. Work plan for the next 18 months of the CRP

– After clarifying the reasons of lower efficiency of the monochromator for minifocusing small-angle neutron scattering (mfSANS) device of Hokkaido University, NPI Rez will prepare new set of crystal wafers.

– Construction of two new horizontally focusing monochromators for KAERI Daejeon and about 10 new crystal slabs (namely Si(111) and Si(220))providing different resolution at different monochromator take-off angles.

– Construction of complete horizontally focusing monochromator for BARC Mumbai

– Preparation of crystal slabs for horizontally and vertically focusing monochromator for BARC Mumbai. The mechanical part will be made in BARC Mumbai.

– Construction of horizontally focusing monochromator for Malaysian Nuclear Agency

– Monte Carlo simulations of parameters of two instruments in KAERI Daejeon. 34

– Presentation of advantageous employment of focusing elements in neutron scattering instruments on international meetings and workshops.

I-2.4. Summary – Results obtained till now under CRP

– Preparation of the monochromator part for (mini)Focusing SANS device designed and constructed by Hokkaido University (main task of the CRP project)

– Construction of focusing monochromator for KAERI Daejeon and 17 crystal slabs for a different monochromator use

– Monte Carlo simulations of optimum parameters of neutron scattering devices for JINR Dubna, KAERI Daejeon, CIAE Beijing, NECSA South Africa

Horizontally focusing monochromator as prepared for JINR Dubna, KAERI Daejeon, BARC Mumbai and Malaysian Nuclear Agency

I-2.5. References

[1] P. Mikula and M. Vrána, performance based on multiple Bragg reflection (MBR) monochromator for high-resolution neutron radiography , Biennial Report 2005-2006, Nuclear Physics Institute, v.v.i., AS CR, Řež near Prague, p.41.

[2] M.K. Moon, C.H. Lee, V.T. Em, P. Mikula, et al., Optimization of Bent Perfect Si(311)- Crystal Monochromator for Residual Strain/Stress Instrument at HANARO Reactor - Part I, Physica B, 369 (2005) 1-7.

[3] M.K. Moon, C.H. Lee, V.T. Em, P. Mikula, et al., Optimization of Bent Perfect Si(220)- Crystal Monochromator for Residual Strain/Stress Instrument- Part II, Physica B- Condensed Matter, 368 (2005) 70-75.

[4] P. Mikula, M. Vrána, V. Wagner, D. Lott, Dispersive Monochromators/Analyzers Based on Cylindrically Bent Perfect Crystals (BPC) for High-Resolution TOF Spectrometry , In th proceedings of the ICANS-XVII-17 Meeting of the Int. Collaboration on Advanced Neutron Sources, April 25-29, 2005, Santa Fe, New Mexico.

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[5] P. Mikula, M. Vrána, D. Lott, V. Wagner, Neutron monochromator based on dispersive double-reflections excited in a cylindrically bent-perfect-crystal (BPC) slab, In Proc. of the ICNS 2005 Conf., Sydney, Nov. 27 – Dec. 2, 2005, Physica B, 385-386 (2006) 1274-1276.

[6] S. Kawamura, J. H. Kaneko, H. Fujimoto, Y. Otake, F. Fujita, A.Homma, T. Sawamura, P. Mikula, M. Furusaka, Deformation experiment of piezoelectric single-crystals for neutron- optical-devices, In Proc. of the ICNS 2005 Conf., Sydney, Nov. 27 – Dec. 2, 2005, Physica B, 385-386 (2006) 1277-1279.

[7] P. Mikula, M. Vrána, V. Wagner, High-resolution neutron diffraction performance for stress/strain measurements in polycrystalline materials , Zeitschrift für Kristallographie, , Suppl. 23 (2006) 205-210.

[8] Y. N. Choi, S.A. Kim, S.K. Kim, S.B. Kim, C.H. Lee, P. Mikula, M. Vrána , Bent perfect crystal (BPC) monochromator at the monochromatic focusing condition , Zeitschrift für Kristallographie, Suppl. 23 (2006) 199-204.

[9] P. Mikula, M. Vrána, V. Wagner, M. Furusaka, Multiple reflections (MR) – a new challenge for high-resolution neutron diffractometry and spectrometry , In Proc. of European Workshop on Neutron Optics NOP07, PSI Willigen, March, 5-7, 2007, Nucl. Instrum. Methods in Phys. Research, Section A, A586 (2008) 18-22.

[10] P. Mikula, M. Vrána, and V. Wagner , Neutron multiple reflections excited in cylindrically bent perfect crystals and their possible use for high-resolution neutron scattering , In the book “Modern Developments in X-ray and Neutron Optics”, eds. A. Erko, M. Idir, T. Krist, A.G. Michette, Springer Berlin/Heidelberg, Volume 137/2008 , pp. 459-470.

[11] R.C. Wimpory, P. Mikula, J. Saroun, T. Poeste, Junghong Li, M Hoffman nand R. Schneider, Efficiency Boost of the Materials Science Diffractometer E3 at BENSC: One Order of Magnitude, Due to a Double Focusing Monochromator , Neutron News, 19 (2008) 16-19.

[12] R.C. Wimpory, P. Mikula, J. Saroun, T. Poeste, R. Schneider, J. Li and M. Hoffmann, Efficiency Boost of the Materials Science Diffractometer E3 at BENSC: One Order of Magnitude, BENSC Experimental Report 2007, HMI Berlin, Edited by U. Stahnke, A. Brandt and H.A. Graf, April 2008, HMI-B 617, ISSN 0936-0891.

[13] M. Furusaka, K. Kamada, Y. Kiyanagi, F. Fumiyuki, A. Homma, K. Ikeda, K. Hirota, H. Shimizu, S. Satoh, P. Mikula, T. Satoh, K. Tanabe, K. Koyama, H. Takahashi, K. Fujita, T. Kamiyama, S. Naito, Y. Kawamura, H. Yoshizawa, S. Ikeda, First results from a mini- focusing Small-Angle Neutron Scattering Instrument (mfSANS) with an ellipsoidal mirror , In Proc. of the Int. Conf. On Advanced Neutron Sources ICANS XVIII, April 26-29,2007, Dongguan, China.

[14] M. Furusaka, T. Satoh, Y. Sasaki, Y. Kawamura, T. Asami, Y. Otake, K. Ikeda, P. Mikula, Y. Kiyanagi, S. Naito, H. Yoshizawa, Installation of a prototype of focusing-type small-angle neutron scattering instrument with an ellipsoidal supermirror, Activity Report on Neutron Scattering Research: Exp. Reports 15 (2008), Report Number: 655, Tokyo University.

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I-3. Development of mini-focus SANS

Main collaborator: Abdul Aziz Mohammed Malaysian Nuclear Agency (Nuclear Malaysia) Kompleks PUSPATI, Bangi 43000 Kajang Selangor MALAYSIA Tel #: 603-89250510; Fax #: 603-89282992 Email: [email protected]

Other collaborators: Azraf Azman , [email protected] Mohd Rizal Mamat, rizal@ nuclearmalaysia.gov.my Megat Harun Al Rashid Megat Ahmad , [email protected] Rafhayudi Jamro , [email protected] Anwar Abdul Rahman, [email protected]

I-3.1. Project Summary

The current SANS system at Malaysian Nuclear Agency is only capable to measure Q in limited range with a PSD (128x128) fixed at 4m from the sample. The existing reactor hall that incorporate this MYSANS facility has a layout that prohibits the rebuilding of MYSANS where the position between the monochromator (HOPG) and sample, and the position between the sample and the PSD cannot be increased for wider Q range.3 2 The flux of the neutron at current sample holder is very low which is around 10 n/cm /sec. Thus it is important to rebuild the MYSANS to maximize the utilization of neutron beams. Over the years, the facility has undergone maintenance and some changes have been made. Modification on secondary shutter and control has been carried out to improve the safety level of the instrument. A compact micro-focus SANS method can suit this objective together with an improve cryostat system. Study of focusing issues (divergence/specular tails) and evaluation and design of micro-focus apparatus for MYSANS facility at Nuclear Malaysia which include design and fabrication of focusing reflector (NiTi) and detector system will be beneficial in term of technology enhancement and human capital development.

In the last meeting, we reported there are four researchers involved in this project. From Oct 2008 two junior researchers have been assigned into this project. It is therefore six researchers are engaged in this project. The following is a brief background of the new members.

Anwar and Rizal are Mechanical Engineers and have been working with the Nuclear Malaysia for 6 years. They are currently undertaking work on Shielding Fabrication for X-ray and Neutron Beam Application. Megat Harun is currently on on-job attachment with Dr Furusaka laboratory at Hokaido University, Japan. His main mission is to design and collecting information on hardware and software for MYSANS micro-focusing technique.Scope of Works

I-3.1.1. Nanostructured alumina materials characterization study

The production of alumina materials with controlled porosity is of considerable interest to the international research and development community. This study has identified that alumina

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with controlled porosity was useful in the electronics industry and set about finding the best method of material preparation and the most appropriate methods of materials characterisation. Alumina nanostructured samples preparations have been carried out at Nuclear Malaysia and SANS characterizations have been performed at SANS BATAN, Indonesia. Analyses of SANS data and modelling of the nanostructured samples are mostly carried out by the Nuclear Malaysia’s MYSANS group.

I-3.1.2. Neutron cooling

Studying the present cryostat design and its performance has been carried out in re-innovating a cooling system that can be enhanced the cooling efficiency and will increase the production of thermal “cooled” neutron. The new system will incorporate improved heat transfer rate, therefore will allow the production of more thermal neutrons. Fluid dynamics calculations will be carried out to model the heat transfer mechanism in the system.

Some works and components have been done in realising these needs. It can be highlighted as follows:

The new liquid nitrogen container is a self-pressurized container. The liquid losses are minimal compared to the current system. The current pumping system used small pump and deliver the liquid through a flexible pipe

Vacuum pump-turbo molecular pumping station which can achieved higher vacuum level up to 1e-6 milibar (Leybold). Previously the cryogenic was pumped using only roughing vacuum pump the pumping level is ~ 1e-2 milibar.

The cryostat which includes the liquid nitrogen (LN2) tank, Beryllium (Be) filters and Cadmiums. The heat transfer from LN2 tank to the Be and Cd is through the thermal

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lingkage which is attach to the tank. The system only achieve 83K after 2 hours and basically need ~ 50 liters of LN2. The losses may also come from the LN2 delivery from the Dewar tank. The LN2 is transfered using a flexible pipe and not properly insulated along the pipe. The delivery is done using the compressed air method. To reduced the losses, we will use the self pressurized tank to deliver the LN2 efficiently.

With the current system, the cryostat is vacuum pump only up to 1e-2 milibar and the tank is not insulated. To improve the cryostat performance, the tank now is insulated using the super insulator – aluminized maylar and the system will be vacuum up to 1e-06 milibar.

To measure the temperature, the current feedthrough thermocouple adapter is not suitable. A new thermocouple feedthrough with four terminals and thermocouple type T replacing the current feedthrough. The feedthrough and thermocouple has been installed at the cryostat.

The thermocouple system also had improved Thermocouple- 4 and installed at the cryostat to measured the terminals Be filters.

Super insulator- The liquid tank is insulated with multilayer Alumanized mylar super insulator –aluminized mylar and vacuum pump up to 1e-6 milibar to minimized / reduced the thermal radiation heat transfer.

I-3.1.3. Neutron shielding

Computational methods have been carried to simulate radiation shielding surrounding an instrument. The Monte Carlo (MC) method is a computational algorithm that can provide approximate solutions to a variety of nuclear and also other physical problems by the simulation of random quantities. MCNP is well known to provide reasonable agreement on result simulation and real experiment. A Monte Carlo simulation of the Malaysian has been performed using MCNP Version 5 code. The determination of flux distribution for TRIGA Mark II PUSPATI (RTP) research reactor and SANS beam port in Malaysia was done based on the Monte Carlo method. The modelling work has been performed to calculate the value of flux distribution i.e. neutron and photon in a SANS facility. The beam port and SANS facility was modelled as close as possible to the real geometry to get the reasonable results. The SANS beam port were modelled in 200 cm length and 20 cm in diameters.

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Fig. 1: Radial Model for the RTP configuration in MCNP 5

Figure 2: SANS beam port (cell no. 409) were modeled in MCNP5 computer Code

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Result:

-2 -1 Cell no. neutron flux (ncm s ) Relative or errors, R

-2 -1 photon flux (pcm s )

10 409 thermal: 9.0856 x10 0.0049

10 fast: 7.6534 x10 0.0129

10 photon: 8.7351 x10 0.0452

I-3.2. Work Plan Year -2008

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Nanostructured Material Characterisations

No Programme / Activities Jan - Apr May – Aug Sept - Dec Notes

3. Design of micro-focusing mirror and funding applications

4. Evaluation of parts/hardwares those to be purchased and fabricated 5. Setup, testing and verification of micro-focusing system and shielding performance – assistance from Hokaido University Cooling System for Neutron Beam Conditioning

No Programme / Activities Jan - Apr May – Aug Sept - Dec Notes

4 Initial testing and system verification 5 Performance evaluation at various reactor powers Shielding Calculation Using MCNP

No Programme / Activities Jan - Apr May – Aug Sept - Dec Notes

3. Simulation and estimation using MCNP for shielding system including collimator system, neutron source and neutron collimator 4. Evaluation of parts, hardware and materials to be purchased and fabricated 5. Setup, testing and verification of shielding performance evaluation

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I-3.2.1. Current Achievement and Results

– MYSANS – enhancement in electronic DAQ – interfacing method using GPIB-USB protocol, data treatment/analysis and easy movement of the flight – installed air lifting footers and collimator tubes.

– – Cryostat – simulation results using 2-D & 3-D geometry using FEA. The result with 2D FEA modelling is accurate and mostly in agreement with the result obtained through experimental.

– MCNP – basic simulation on MYSANS shielding setup.

– Sample – prepared and characterise using BATAN, SANS and other related techniques, i.e. TEM, XRD. I-3.3. Work Plan For The Year 2009

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Nanostructured Material Characterisations

No Programme / Activities Jul – Dec 2009 Jan – Jun 2010 Jul – Dec 2010 Notes

1. Sample preparation for measurement at SANS facility in BATAN and data analyses and programming 2. Design of micro-focusing system, shielding components and funding applications – assistance from Hokkaido University 3. Procurement preparation for parts/hardware/materials to be purchased and fabricated

Cooling System for Neutron Beam Conditioning

No Programme / Activities Jul – Dec 2009 Jan – Jun 2010 Jul – Dec 2010 Notes

1. Implementation of heat transfer mathematical models and cryostat redesign parameters 2. Models discrimination and parameters estimation using Computational Fluid Dynamic (CFD) software. (To model with 3D analysis and repeat experimental testing to verify our design and simulation data.) 3. Purchase of hardware and related controlled components for cryostat modification

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Beamline Upgrading

No Programme / Activities Jul – Dec 2009 Jan – Jun 2010 Jul – Dec 2010 Notes

1 Flight tube positioning and alignment.

2 Modification of front collimator external shielding.

Monte Carlo Simulation: MCNP - Shielding Calculation

No Programme / Activities Jul – Dec 2009 Jan – Jun 2010 Jul – Dec 2010 Notes

1. Expansion of the MCNP5 modelling to the whole SANS beam port and SANS facility. 2. Evaluation of computing hardware and software items to be purchased 3. Testing and verification of instrument characteristics and performance

Monte Carlo Simulation: McStas Beam Instrument Calculation

No Programme / Activities Jul – Dec 2009 Jan – Jun 2010 Jul – Dec 2010 Notes

1. Evaluation of SANS existing set-up and set-up with reflection/focusing mirror 2. Testing and verification of instrument characteristics and performance

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46

I-4. SANS BATAN: Improvement the Neutron Intensity by Focusing Optics

Edy Giri Rachman Putra, Epung S. Bahrum, Eddy Santoso, Bharoto

Neutron Scattering Laboratory

Center for Technology of Nuclear Industrial Materials

National Nuclear Energy Agency of Indonesia (BATAN)

Gedung 40 Kawasan Puspiptek Serpong, Tangerang 15314, Indonesia

Tel. +62 21 7566727, Fax. +62 21 7560926, email [email protected]

I-4.1. Introduction

A small-angle neutron scattering (SANS) technique has been pointed out as a major tool which provides essential information about the fundamental structures of materials in the nanometer scale, 1 – 100 nm. The 36 meter SANS BATAN spectrometer (SMARTer) as the second largest SANS spectrometers in the Asia-Oceania nowadays was installed at the end of 49 meter guide tube of the 30 MW multi-purpose reactor G.A. Siwabessy (RSG-GAS) in Serpong, Indonesia. Until 2004, the spectrometer was not well utilized due to a shortage in staff members, instrument failures, and an undefined long-term research program. Then, a five-year in-house work plan was proposed to replace, change, and upgrade gradually the instrument (i.e. electronics, mechanics, computer software).

In the last three years, the spectrometer has been revitalized and gradually developed on the control system, experiment methods, data collection, and reduction with the intention of improving its performance [1,2]. Many good results confirmed by Dr. P.S. Goyal of BARC, India, Dr. J. Kolhbrecher of PSI, Switzerland and Dr. P. A. Timmins of ILL, France as IAEA expert missions to BATAN in 2005, 2006, and 2007 respectively have been taken from SANS BATAN spectrometer. A nearly monodisperse dilute solution of polystyrene latex standard sample was characterized at several experimental settings, Fig. 1. From Fig. 1, it is noticeably showing the smeared scattering pattern with a shorter neutron wavelength, 0.39 nm (3.9 Å) compare to a larger wavelength, 0.57 nm (5.7 Å). The appearance of the oscillation is more pronounce with a good resolution using a larger wavelength. It can be verified that SANS spectrometer is more powerful (high resolution with high intensity) using a larger neutron wavelength or cold neutron.

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Figure 1. A monodisperse polystyrene latex sample measured at various experimental settings[2].

Whereas the neutron source is produced from the low-medium flux neutron of 30 MW thermal reactor RSG-GAS which operates regularly at 15 MW, one half of its maximum power, the spectra of the Maxwellian distribution has a maximum neutron flux at a neutron wavelength c.a. 0.1 nm (1 Å). Consequently, the neutron flux at a larger wavelength ~ 1 nm (10 Å) decreases theoretically by magnitude of three [3]. In Fig. 1 showed that the intensity decreases by magnitude of one as the neutron wavelength increases from 0.39 nm (3.9 Å) to 0.57 nm (5.7 Å). This circumstance may not be accepted for a neutron scattering experiment, especially for SANS. For that reason, it is significantly needed to improve the neutron intensity as well as the resolution by designing the new collimator system using a focusing device. The implementation of the focusing device, such as optical lenses or magnetic lenses, the neutron flux or intensity will be gained theoretically by one or two order of magnitude and also improving the minimum Q (momentum transfer) of conventional SANS[4,5]. Those improvements are definitely required to benefit the instrument itself and for researchers to do the scientific works.

References:

1. Edy Giri Rachman Putra, et al., J. Appl. Cryst. 40 (2007) s447 – s452. 2. Edy Giri Rachman Putra, et al., J. Nucl. Instrum. Methods. A 600 (2009) 198 – 202. 3. http://www.frm2.tum.de/en/technik/secondary-sources/index.html 4. S.-M. Choi, et al., J. Appl. Cryst. 33 (2000) 793 – 796. 5. http://sans.web.psi.ch/sansstatus/nlenses.html

I-4.2. The works have been done

Mapping the neutron flux at a various configurations of the spectrometer which is the first work plan of the research contract has been carried out. The neutron flux or intensity at the sample position as a function of collimation length, a distance from the sample position to neutron source (Fig. 2), with a different neutron wavelength has been measured by a foil method, Analysis (NAA). The collimation length which varied for 1.5, 4, 8, 13, and 18 m contributes to the optimum result of the neutron scattering distribution, due to the beam divergence. Meanwhile the effect of neutron wavelength on neutron intensity was

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studied at 5.7 Å (3500 rpm), 3.9 Å (5000 rpm), and 3.2 Å (3500 rpm) at a fixed collimation length.

Sample position

Figure 2. A schematic drawing of a 36 m SANS BATAN spectrometer in Serpong, Indonesia

The flux measurements were also performed at the end of neutron guide (just before the velocity selector) and after the selector (just before the collimation system). These data correspond to the intensity of the white and the monochromatised neutron beam, respectively. The gold foils mounted at a certain diameter of cadmium plate and then were exposed with neutron beam at a various positions, collimation length and neutron wavelength. The gamma- ray from the activated gold foils was then measured using an HPGe detector gamma-ray spectrometer and analyzed using a multi-channel198 analyzer (MCA). This measured gamma-ray count rate is useful to calculate the activity198 of Au in each gold foil. With the purpose of calculation the activity of the activated Au, the efficiency198 of HPGe detector, irradiation time, cooling or decay time, radioactive half-time of 198Au , number of atoms and are required. From the activity of Au calculation, then the neutron flux or intensity at SANS spectrometer with several setting configuration can be distinguished.

Figure 3 . The neutron flux profiles after the velocity selector (MVS) and at sample position as a function of collimation length.

From the flux measurement showed that the flux of the white neutron8 beam at the-2 end-1 of the neutron guide (just before the velocity selector, MVS) is 6.57 × 10 neutron cm s . After the velocity selector the neutron intensity which is defined as 0 m of collimation length will be depending on the speed of selector, i.e. 3.2 Å (7000 rpm), 3.9 Å (5000 rpm) and 5.7 Å (3500 rpm), Fig. 3. It noticed that the monochromatised neutron intensity generally decreases by magnitude of one than the white beam. As the collimation length increases from 1.5 m to 49

18 m, the neutron intensity decreases exponentially. In total, the intensity of all monochromatised neutron wavelengths decreases by magnitude of two using the longest collimation length configuration 18-meter. In the other hand, the longer neutron wavelength 5.7 Å decreases by magnitude of one compared to the shorted neutron wavelength 3.2 Å at the longest collimation length configuration.

From the neutron intensity mapping at SMARTer can be concluded that in obtaining the highest as possible of neutron intensity without losing the resolution, the neutron source has to close as possible to the sample. This circumstance is very difficult to be accomplished by a conventional SANS (pinhole SANS). Therefore, a focusing SANS has to be developed in improving the intensity as well as the resolution.

The Monte Carlo calculation program (McStas) has been installed at the Neutron Scattering Laboratory of BATAN and then applied for testing and practicing. Vanadium sample can, Debye Scherrer sample model and Maxwellian distribution profile model have been simulated with the intention of being familiar with the program.

I-4.3. Objectives

The overall objectives of this CRP are:

1. To stimulate and initiate the improvement and development of 36 m SANS BATAN.

2. To explore the possibility of applying the focusing devices on the collimation system of 36 m SANS BATAN.

3. To establish SANS experiments in materials science & biology research in the wide- scattering-vector-range.

I-4.4. The proposed works

The proposed works that have to be done in the coming years:

1. Workshop / Training Course / On Job Training (OJT) on Monte Carlo calculation program – theory and applications, through IAEA's TC program, i.e. IAEA Expert Mission for local neutron scattering scientists (2009). The Monte Carlo calculation program for development of neutron instrument has to be exposed initially to the local scientists.

2. A simulation using a Monte Carlo calculation program to calculate the theoretical intensity and profile patterns at SANS spectrometer with a various configuration (2009 – 2010).

3. Joining either the NPI in Czech Republic or JINR in Russia for enhancing the knowledge and experience of one Indonesian neutron scattering scientist on designing and developing the new focusing lens of SANS BATAN (2010).

4. Implementation of the detector monitor, pre-Amplifier and its electronics system for present count data acquisition (2010).

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I-4.5. Expected Outputs:

The outputs from this CRP will be:

– Neutron flux characteristic map at 36 m SANS BATAN spectrometer.

– Analytical calculation of the optimum design of optical focusing devices at 36 m SANS BATAN spectrometer.

– Implementation and performing of the optical focusing devices at 36 m SANS BATAN spectrometer.

– Monitor count normalization / absolute scale for all SANS measurements.

– Scientific publications, journal papers, and institutional report and presentation at national and international meetings.

I-4.6. Conclusions

From this work and collaboration under the CRP project, we would like to stimulate and initiate the improvement and development of 36 m SANS BATAN spectrometer and also to explore the possibility of applying the optical focusing devices at the collimation system.

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ANNEX II. MODERATOR DEVELOPMENT

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II-1. Development of very cold moderator materials at the low energy neutron source

David V. Baxter and W. Michael Snow

Email: [email protected] Email: [email protected]

Indiana University Cyclotron Facility 2401 Milo B. Sampson Lane, Bloomington, IN 47408 FAX: (812) 855-6645

II-1.1. Project Summary

The Low-Energy Neutron Source (LENS) at Indiana University provides a unique resource for the development of new very cold moderator materials and designs. LENS represents an explicit demonstration of a neutron scattering facility that provides sufficient flux for performing materials research with a very limited construction budget. As such, through its operation the facility represents precisely the sort of facility that the originators of the CRP envisioned promoting. The LENS moderator is capable of operating at temperatures below 4 K, although typical operations use a temperature of 6K to allow a He cover gas over the moderator. Construction materials and designs for the LENS target and moderator assemblies have been chosen to provide convenient access to the moderator in order to facilitate studies of prototype designs by limiting activation in this area. Thus the primary focus of our participation in this CRP will be a series of experiments relevant to the development of very cold neutron moderators suitable for future low, medium, and high energy spallation sources. These experiments will include total neutron cross-section measurements on candidate materials over a wide range of neutron energies and explicit tests of prototype neutron moderator designs. The project will also include the development of scattering kernels suitable for use in MCNP modelling of future neutron sources.

II-1.2. Recent Accomplishments and background information

II-1.2.1. CRP-related accomplishments to date

The group at IUCF started construction of the LENS facility in 2003, and we have been producing neutrons since Dec. 2004, and cold neutrons since April 2005 [1,2,3]. This source produces neutrons though (p,nX) reactions on a Be target, and converts these primary neutrons to long-pulse cold neutron beams suitable for materials research through the use of a coupled solid methane moderator operating at temperatures below 10K. In July 2007 we started commissioning a second target station and an improved SANS instrument and have recently completed upgrades to the RF power systems and accelerator to increase the proton beam energy to 13MeV. Today beam powers of 4kW are routinely delivered to the target and power levels of 6kW have been demonstrated over periods of several hours. We anticipate operations at up to 10kW over the next year.

Our primary goal in association with this CRP is the development and modelling of moderators suitable for very cold neutron (VCN) production; this is also a major facility goal for LENS. This work will involve at least three different thrusts. First, all of the instruments at LENS will exhibit increased performance as the spectral temperature of the moderator is reduced, and hence we will be changing details of how the moderator is operated as well as its

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physical design to reduce that temperature. Second, we will explore new materials (primarily through total cross section measurements) that may be suitable for VCN production, and collaborate with others within the CRP on modelling the neutronic behaviour of those materials. Finally, we will develop some computer modelling tools ourselves for certain materials (such as phase II solid methane). There are, however, additional activities planned at LENS that also have potential overlap with CRP participants. We have developed and have just begun commissioning a instrument based on the so-called SESAME (Spin Echo Scattering Angle MEasurement) principle of Roger Pynn instrument to extend the range of SANS to larger length scales and demonstrate the possibility of high-precision spin- manipulation instruments on a long-pulsed source. Such innovations in neutron instrumentation demonstrate a key role such small sources can play in supporting the international neutron scattering community. Finally, LENS is actively collaborating with researchers in the neutronics groups at the SNS, LANSCE, and ISIS neutron scattering facilities to increase our understanding of how to effectively model moderator performance on the computer (especially for long wavelengths). These last two activities serve as explicit examples of the type of collaboration between small-scale and international-scale sources that the CRP envisions fostering.

As indicated above in the project summary, operation of LENS itself constitutes a significant contribution to the overall goals of the CRP. We are presently operating the facility under a three-year agreement with Indiana University to use internal funds for stewardship while being used by University researchers. We will be submitting a proposal to the National Science foundation to augment this support to broaden the access to the facility to include researchers from across the region and, we hope, even further afield. During the construction phase we have engaged in a number of measurements of moderator spectra. The neutron spectral temperature achieved initially (roughly 30K) was higher than we had expected, and several of these experiments have been directed toward lowering this temperature. We have introduced both water (at room temperature) and cold polyethylene in order to improve the coupling of the cold source and have driven the spectral temperature closer to 20K as a result. A figure showing the neutron spectrum an its description in terms of three Maxwellian peaks and one slowing-down spectrum is shown below.

10 8 C)

µ 10 7

10 6 E I(E)E (n/sR.

10 5 10 -4 10 -3 10 -2 10 -1 10 0 10 1

E (eV)

Fig. 1: Typical spectrum from the LENS moderator together with a fit to three Maxwellians (at roughly 210, 57, and 18K) and a slowing-down function.

In parallel with the efforts described above, we have developed a scattering kernel for modelling phase II solid methane in MCNP calculations. This kernel takes full account of the

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total molecular spin and is able to provide detailed insight in the contributions of the various excitations (phonons, rotations, librations, and tunnelling) in the material to its moderating characteristics. Already we have seen that this kernel behaves differently than the smeth22k [4] kernel that had previously been considered to be the state-of-the-art for methane. The newer kernel is better able to follow the observed energy dependence of the neutron total cross section at 4K than is smeth22K [5,6]. Moreover, when used with the LENS TMR geometry, the new kernel predicts slightly lower intensity than the smeth22K kernel for energies below 10 meV and slightly higher intensity from 10meV to 1eV. In addition, our simulations with the smeth22K kernel indicated negligible differences between the neutron spectra between moderators of 1 cm thickness or 2 cm thickness (when fed by the light-water reflector at LENS). Simulations with our new kernel indicate that a 2-cm thick methane moderator could be expected to show increased brightness. This was the motivation for our addition of the cold polyethylene premoderator. Interestingly, the same model indicates that the rotational modes in phase II methane contribute the majority of the spectral weight to the scattering law of this material (S(Q,w)) at low energies (see figure 2) even though only ¼ of the molecules are freely rotating below 20K, and the tunnelling modes available to the other ¾ of the molecules have smaller energy excitations associated with them than the free rotor states [7]. This suggests that liberating additional free rotors (such as through alloying with Ar, which is purported to suppress the orientational phase transition at 20K [5]) could lead to a more effective moderator. We have made two attempts at realizing this, but to date have not succeeded in producing moderators with sufficient Ar to achieve the desired result.

Fig. 2: S(Q,w) for methane in phase II as predicted by our kernel. The contribution on the left is from free rotors, the (smaller) contribution on the right is that from the hindered rotors [6].

In support of our work to develop neutrons in the VCN range, we have noticed that existing evaluated nuclear data files (which are used as input to the Monte Carlo codes that will be used to design any future VCN source) are typically not accurate below 1meV even for such common materials as water and [8]. We have therefore started a program of total cross-section measurements on materials of interest to VCN production, starting with water and ZrH2 In this work we have clearly demonstrated our ability to measure such cross- sections down to energies on the order of 100 µeV, and we have reason to believe that we can reduce this lower limit even further.

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Fig. 3: Comparison of preliminary analysis of data taken recently at LENS (red curve) with literature data for the total cross section of ZrH2. This demonstrates our ability to measure such data down to energies at least as low as 0.1 meV.

II-1.3. Planned Future Work

Over the next 18 months, we will continue to conduct total cross-section measurements of various materials that may be suitable for future VCN moderators. Specific examples to be explored include mesitylene, methanol, toluene, and methane (and, we hope, deuterated versions of these as well). Mixtures of these materials (and others) will also be used in an effort to develop candidate amorphous moderator materials (for which there will be additional low-energy modes, and in which may be less of an issue). Our goals will be to provide data to other CRP members who are also interested in scattering kernel development, and to demonstrate materials that may prove useful for application in future VCN moderators. We will also continue more quantitative assessment of the scattering kernel developed during the first year of the project.

In addition to this work, we will continue our collaboration with several major neutron sources exploring novel neutron moderator designs. Some of this work is directed at lowering the spectral temperature, but much is also simply concerned with increasing moderator brightness, controlling emission time distributions, and increasing our confidence in the scattering kernels that lie at the heart of the simulation codes that are used in source design. We also expect to work with other members of the CRP (and others) to investigate the impact of incoherent inelastic scattering on Small Angle Neutron Scattering. In particular, we wish to investigate whether detailed analysis of the total cross section of a sample can provide any insight into this contribution to the SANS background.

II-1.4. REFERENCES

1. C. M. Lavelle, et al., “Neutronic Design and Measured Performance of the Low Energy Neutron Source Target Moderator Reflector System”, Nucl. Instr. Meth., A587, p324-341 (2008). 2. D. V. Baxter, et al., “ Status of the Low Energy Neutron Source at Indiana University” , Nucl. Instr. Meth. B 241 209-212 (2005).

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3. R. E. MacFarlane, p221-231 “Cold neutron scattering kernel methods,” in J. M. Carpenter, E. Iverson, “International Workshop on Cold Neutron Moderators for Pulsed Neutron Sources,” OECD OCDE, Argonne National Laboratories, 1997. 4. M. Prager, B. Asmussen, W. Press, H. Blank, C. J. Carlile, “Rotational Spectra and the phase diagram of CH4/Ar mixtures,” J. Chem. Phys. 95, 569-575 (1991). 5. Y Shin, et al., “A microscopic model for the neutron dynamic structure factor of solid methane in phase II,” submitted to Phys. Rev. June 2009, arXiv:0705.0824. 6. S. Grieger, H. Friedrich, K. Guckelsberger, R. Scherm, and W. Press, “The total neutron cross section of solid methane in phase II,” J. Chem. Phys. 109, 3161-74 (1998). 7. See, for instance, “ Thermal Neutron Scattering Data for the Moderator Materials H 2O, D2O, and ZrH x in ENDF-6 Format and as ACE Library for MCNP(X) Codes”, M. Mattes, and J. Keinert, IAEA report INDC(NDS)-0470 (2005), Figs. 4-16 and 6-8. th 8. D. V. Baxter, et al., “The Low Energy Neutron Source—Status and Prospects“, p 18, 17 Meeting of the International Collaboration on Advanced Neutron Sources, Santa Fe, NM, April, 2005 LANL LA-UR-06-3904 (2006).

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II-2. Modelling and measurements of neutronic properties of new cryogenic neutron moderators

Main collaborators: José Rolando GRANADA, Javier Roberto SANTISTEBAN

Centro Atómico Bariloche Comisión Nacional de Energía Atómica (CNEA) ARGENTINA

Other collaborators: Javier DAWIDOWSKI, Florencia CANTARGI, Aureliano TARTAGLIONE, Sergio PETRIW, Jerónimo BLOSTEIN, Luis CAPARARO

II-2.1. Short Summary of Work related to this Contract

Within the frame of the present Contract, the activities at Neutron Physics Division of Centro Atómico Bariloche involved theoretical, calculational and experimental aspects related to the study of hydrogeneous materials of interest as cold moderators.

The development of scattering kernels for a number of molecular systems was completed, including a set of hydrogeneous methylated aromatics such as toluene, mesitylene, and mixtures of those. In order to partially validate those new libraries, we compared predicted total cross sections with experimental data obtained in our laboratory.

In addition, we have introduced a new model to describe the interaction of slow neutrons with solid methane in phase II (that is the stable phase below T=20.4K and atmospheric pressure). Very recently, a new scattering kernel to describe the interaction of slow neutrons with solid Deuterium was developed. The main dynamical characteristics of that system are contained in the formalism; the elastic processes involving coherent and incoherent contributions are fully described, as well as the spin-correlation effects.

The request of a specific cross section libraryst for light water ice at 100K, formulated by Mr. Saibal Basu from BARC, India, during the 1 . RCM held in Sapporo, Japan (July 2007), was satisfied, and a file containing the cross section data in a format appropriate for MCNP calculations was sent to him.

Within these subjects, two PhD Thesis were completed by members of our group during the last three years, under the supervision of the Chief Scientific Investigator. The new cold moderator system for our electron LINAC based pulsed neutron source was designed and optimized, and it is now under construction.

II-2.2. Scientific Scope of our Project under this CRP

Cold neutrons are widely used in different fields of research such as the study of the structure and dynamics of solids and liquids, the investigation of magnetic materials, biological systems, polymer science, and a rapidly growing area of industrial applications.

The development and optimization of advanced cold neutron sources require neutronic calculations involving thermal and subthermal neutron energies, which in turn demand the

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knowledge of reliable cross section data relative to the materials which conform the system under consideration. The compromise solution adopted in standard Nuclear Data Libraries involves the inclusion of scattering cross sections for a few common moderators at some selected temperatures, and data for any different material or physical condition must be ‘constructed’ from pieces of information actually corresponding to those few cases found in the existing files.

Within this project we will complete the development of scattering kernels for a number of molecular systems of interest as cold moderator materials, with particular emphasis on methane and hydrogeneous methylated aromatics such as toluene, mesitylene, xylene, and mixtures of those, including for some special cases consideration of their different solid phases. In order to validate those new libraries, we expect to compare predicted total cross sections and neutron spectra with experimental data obtained in our laboratory and at other facilities, like LENS at Indiana University and the Hokkaido LINAC.

During a second phase of this project, we will tackle the problem of describing the interaction of slow-neutrons with deuterated molecular solids, typically d-methane, d-mesitylene, and solid deuterium at vey low temperatures.

Finally, we will construct the new cold source at our electron LINAC based neutron source, which has been designed and optimized according to a modular concept that offers great flexibility in terms of neutron intensity and pulse width.

II-2.3. Detailed Work Plan for the next 18 months

Having completed the first phase of our project, and as it was indicated above, we will tackle during the next period the case of deuterated systems. Those materials are of primary interest as moderators for very- and ultra-cold neutrons, on account of their very small absorption cross sections and the expected shift in the excitation energies due to isotopic effects. Although interference phenomena revealed by the large coherent scattering length of Deuterium play no major role in the thermalization process, it will be useful to take it into account in order to compare model predictions with (single) scattering experiments.

One of those systems, solid deuterium, has been already considered in a preliminary way, achieving highly encouraging agreement with the scarce experimental information available. Specifically, we propose to work during the next 18 months to accomplish the following goals:

– To produce scattering kernels for several deuterated materials of interest as cold-, very cold-, and ultra cold-neutron moderators, the list will include solid deuterium, solid d- methane, and deuterated solid aromatic hydrocarbons.

– To generate and validate the cross section libraries for those materials over a wide range of temperatures, in a format appropriate for MCNP calculations;

– To propose new composite deuterated materials that could give an enhanced performance in terms of long wavelength neutron production and radiolysis resilience;

– To improve our experimental capabilities by operation of a new cold source in our pulsed facility;

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– To strengthen multilateral cooperation between groups involved in the improvement of experimental capabilities or techniques around neutron facility centers;

– To disseminate the new knowledge and developments related to advanced cold moderators through scientific publications and presentations in national and international meetings.

II-2.4. Results obtained under this CRP

As it is reflected through our recent contributions in matters related to the present Project (ANNEX), activities are in progress at Neutron Physics Division in theoretical, calculational and experimental aspects involving the study of hydrogeneous materials of interest as cold moderators.

We reviewed the dynamics of a group of aromatic hydrogenous solids, and making use of existing experimental information on the density of states for translational and rotational (librational) motions, we developed synthetic frequency spectra for them. Cross section libraries in ACE format were then generated using the NJOY code. They were validated by comparing with experimental data obtained in our laboratory and used to predict neutron spectra emerging from a typical TMR configuration, by using the MNCP code for the evaluation of the energy distribution of neutrons coming out from the cold moderator.

Although solid methane is the best moderator in terms of cold neutron production, it has very poor radiation resistance, causing spontaneous burping even at fairly low doses. Such effect is considerably reduced in the aromatic hydrocarbons. On the other hand, all of them show a similar and significant neutron production, with the exception of benzene. Even though those aromatic materials are very easy to handle, the solid phases that produce an enhanced flux of cold neutrons correspond to amorphous structures rich in low-energy excitations, and they can be created through lengthy cooling processes requiring in many cases additional annealing stages. The 3:2 mesitylene-toluene mixture, that forms in a simple and direct manner the appropriate disordered structure, constitutes an excellent cryogenic moderator material, as it is able to produce an intense flux of cold neutrons while presenting high resistance to radiation, thus conforming a new and advantageous alternative to traditional moderator materials (Figs. A1, A2).

We developed a simple model to describe the interaction of slow neutrons with solid methane in phase II, including the main dynamical features of the system and the effect of spin correlations. This effect occurs in molecules containing identical nuclei whenever spin and rotational states are coupled, thus imposing symmetry requirements on the molecular wave function. The model is not intended to produce a detailed description of the neutron interaction with the isolated quantum excitations of the system, as it is based on simple frequency spectra to represent the molecular translational and rotational motions and Einstein oscillators for the vibrational motion. A central motivation for the development of this new scattering kernel has been the generation of cross section libraries appropriate for the calculation of neutron thermalization properties in CH 4 II. Its predictions are in good agreement with a quantum mechanical calculation over the limited range where the latter was formulated, and with available experimental information over the complete thermal energy range. Bearing in mind the general nature of the approximations involved in the present prescription, and besides its predictive capacity demonstrated for solid methane in phase II, the model can be useful for the analysis of neutron scattering experiments designed to study spin species conversion of different rotational tunneling molecules at low temperatures, or in

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a wider context, to perform reliable multiple-scattering corrections in experiments oriented to precise determinations of density of states (Figs. A3, A4).

Very recently, a new scattering kernel to describe the interaction of slow neutrons with solid Deuterium was developed. The main characteristics of that system are contained in the formalism, including the lattice’s density of states, the Young-Koppel quantum treatment of the rotations, and the internal molecular vibrations. The elastic processes involving coherent and incoherent contributions are fully described, as well as the spin-correlation effects. The results from the new model were compared with the best available experimental data, showing very good agreement (Figs. A5, A6).

Finally, we wish to emphasize that the new neutron cross section libraries produced in the context of this project constitute a valuable addition to the international effort for the development of advanced cold neutron sources. Within these subjects, two PhD Thesis were completed by members of our group during the last three years, under the supervision of the Chief Scientific Investigator.

1200

1000 MESITYLENE

800 32K

600

(Phase III) 400

Experim. Calcul. Total Cross (barns) Section Experiments 200 1E-3 0.01 0.1 1 using the E (eV) Bariloche LINAC

Fig. A1: Comparison of measured and predicted total cross section of Mesitylene at 32K, according to our new scattering kernel.

Mixture

Mesi/Tol 1000 (3:2) 800 MESI (3:2) TOL 32 K

600

400

Experim. Calcul. Total Cross Section (barns) Section Cross Total

200 1E-3 0.01 0.1 1 E (eV)

Fig. A2: Comparison of measured and predicted total cross section of a mixture of Mesityl and Toluene, according to our new scattering kernel.

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Scattering Function for solid Methane in Phase II

50

40 5K

30 S(α,β)=(kBT/ħ) S(Q,ω) 20

10 2 2 10 α=ħ Q /2Mk BT ~y

8 01 β=ħω/kBT ~x 2 6 3 y

x 4 4

Fig. A3: The scattering function for Methane at 5K (phase II), according to our new model.

Comparison of calculated σT(E) with experimental data of Grieger et al.

J.Chem.Phys. 109 ,3161 (1998)

800

600 0.3K

400

10K

Total Cross(barn) Section Total 200

1E-4 1E-3 0.01 E (eV)

Fig. A4: Comparison of measurements and our predictions for Methane II.

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20.0 Model oD 2

Model nD 2 17.5 Seiffert 17K 15.0 PSI 18K

12.5

10.0 X-Section (b)

7.5

5.0

2.5 1E-3 0.01 0.1

Energy (eV)

CENTRO ATOMICO BARILOCHE - ARGENTINA

Fig. A5: Comparison of measured with our calculated cross sections of ortho- and normalSolid deuterium at 18K.

70 30 35 E = 0.00001 eV 5K 60 25 30 E = 0.001 eV E = 0.0001 eV oD5k pD5k 50 pD5k 25 20 oD5k pD5k 40 20 oD5k 15 (E,E´) (E,E´) 30 σ 15 (E,E´) σ 10 σ 20 10

10 5 5

0 0 0 0.000 0.002 0.004 0.006 0.008 0.010 0.012 0.000 0.002 0.004 0.006 0.008 0.010 0.012 0.000 0.005 0.010 0.015 E´(eV) E´(eV) E´(eV)

300 12K

80 80 250

200 60 pD12k pD12k 60 pD12k oD12k oD12k oD12k 150 (E,E´) (E,E´) σ (E,E´) 40

σ 40 σ 100

20 20 50

0 0 0 0.000 0.005 0.010 0.015 0.000 0.005 0.010 0.015 0.000 0.005 0.010 0.015 0.020

E´(eV) E´(eV) E´(eV)

CENTRO ATOMICO BARILOCHE - ARGENTINA

Fig. A6: Energy-transfer kernels for solid ortho- and para- deuterium at different incident neutron energies.

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II-3. Development of Cryogenic Moderators Using a Small Proton Accelerator

Yoshiaki Kiyanagi*, Fujio Hiraga, Takashi Kamiyama, Akira Homma, Fumiyuki Fujita and Michihiro Furusaka

Division of Quantum Science and Engineering, Graduate School of Engineering, Hokkaido University, Kita-13, Nishi-8, Kita-ku, Sapporo 060-8628, Japan

* Contact person, Fax. +81-11-706-7368, E-mail: [email protected]

II-3.1. Short Summary of Works Performed in Our Group

During the last 3-4 years the authors have studied the following neutron moderators combined with accelerator-based neutron sources to supply the short pulse cold neutrons.

II-3.1.1. Para-hydrogen Moderators

Liquid para-hydrogen has smaller scattering cross section than those of normal hydrogen at an energy region below about 15 meV, and the para-rich-hydrogen moderators might decrease the width of the cold neutron pulses emitted from the moderators due to low up-scattering cross-section in para-hydrogen. We developed a hydrogen gas supply system to convert ortho-hydrogen to para-hydrogen using an iron hydroxide (Fe (OH) 3 ) catalyst and an ortho/para ratio measuring apparatus using the Pirani gauges. The para-rich-hydrogen gas was cooled and condensed into the moderator chamber equipped with the pulsed fast neutron source at the Hokkaido University 45MeV Linac. We obtained the flight time spectra of neutrons from the moderator chamber. It turned out that in the case of the decoupled moderator the momentary maxima of the cold neutron pulses from the para-rich-hydrogen moderator were larger than those of the normal hydrogen moderator in the cold neutron energy region. This result on the para-rich-hydrogen moderator shows the excellence as a short pulsed neutron moderator when we cannot use the methane moderator.

In the case of the coupled moderator, we can get much higher intensity than the normal hydrogen moderator and the intensity is almost the same as that of the coupled methane moderator.

II-3.1.2. Grooved Solid Methane and Solid Mesitylene Moderators

A cold moderator having a groove for extracting a neutron beam from the inside of the moderator might increase the cold neutron intensity around the bottom of the groove. The intensity distributions of neutrons emitted from the solid methane moderator and the solid mesitylene moderator having a single groove were calculated by MCNPX. The dependence of the cold neutron intensity on the dimensions and the configuration of the groove was examined. The optimal condition of the groove size and the position was found, and it was turned out that the intensity from the groove of the mesitylene moderator was almost the same as that of the methane moderator.

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II-3.2. Scientific Scope of Our Project under the CRP

With the growing need for intense neutrons in various applications such as the nondestructive inspection in industrial use, the - therapy in medical treatment and the technology to detect a hidden in homeland security, the necessity for small accelerator-based neutron sources is increasing such as a fixed type having an intensity of 13 12 about 3×10 (n/s) and a movable type with an intensity of about 1×10 (n/s). Neutron facilities for material research based on a small accelerator are desired to be constructed as well as a high power accelerator based one.

Recently, the 3 m long proton linear accelerator (small proton linac) with a weight of 2.7 t has 1) been developed. The light weight and compact size of the small proton linac makes it easily to transport and allow flexibility for installation in any facility with a low construction cost. The small proton linac emits protons with energy up to 3 MeV under the condition of 100 pulses per second, 100µs pulse width, and 100µA beam current. The proton beam current can be increased up to 2.5 mA by using the klystron as a rf power supply and the electron cyclotron resonance device as an ion source.

13 9 The total neutron output of 3×10 (1/s) may be achieved by using the combination of Be target with the small proton linac that emits protons accelerated up to 11 MeV in a beam of 2) 9 1.4 mA. Thus the Be neutron source equipped with cold moderators as well as focusing devices for cold neutrons may increase the momentary maxima of the cold neutron pulse and is applicable for wide fields of material research using neutron scattering experiments. 9 Moreover, the Be neutron source with a specific moderator is also applicable to the boron- neutron capture therapy requiring intense epithermal, thermal or cold neutrons.

12 The 1×10 (1/s) neutrons with energies up to 800 keV can be generated by using the 7Li target combined with the small proton linac emitting about 2.5 MeV protons at current of 1 mA.3) The low energy neutrons created by the 7Li (p, n) reaction will increase an efficiency of moderation in a moderator and decrease shielding required for a facility. Thus the neutron facility based on the 7Li neutron source will become compact and have capability to be used in many places in manner of a moving trailer. The transportable 7Li neutron source may also promote the use of neutrons for technologies in homeland security.

II-3.3. Detailed Work Plan for the Next 18 Months

7 When we use the Li (p, n) reaction to produce neutrons, γ-rays of 14MeV or higher energy 7 may be generated by the resonance capture of protons of 411 keV by Li. The yield of 4) photons of 14MeV were roughly estimated and not yet measured. The results that we have calculated so far showed that the photons of 14MeV strongly dominate the surface photon 7 dose on the shielding components around the Li (p, n) cold neutron source. Thus we are 7 planning to measure the yield and the spectrum of the photons that are generated by the Li (p, n) reactions in a thin Li target equipped with the 3 MeV Pelletron accelerator of the Research Laboratory for Nuclear Reactors at the Tokyo Institute of Technology. However, the research fund has not been acquired.

For the development of a fixed type intense neutron source for neutron scattering experiments, we will also perform R&D to look for the best materials and a configuration for 9 a coupled methane moderator system consisting of a Be target, a pre-moderator and a reflector as well as a moderator. Furthermore, a mesitylene moderator system will be also studied since it is much preferable than the methane one in the facilities having a serious

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safety regulation, and new materials, if they exist, will be also studied. From this research we 9 will design the best moderator system for the combination of the Be (p, n) reactions with the small proton linac.

We have planed the following items but the budget for these researches is partly confirmed and we need other sources for the researches.

1. Simulation Calculation to Obtain the Optimal System of Coupled Methane Moderators

We will study a slab shape moderator to obtain optimal condition of the moderator system to get the highest performance. Combination of moderator material, premoderator and reflector is studied in more detail. The configuration to get beam lines as many as possible is an important issue to accelerate the neutron scattering experiments. Therefore, we also examine the method to get many beam lines at one neutron moderator system.

Furthermore, we will study a coaxial cylindrical moderator with an inside pre-moderator and an outside methane moderator to increase the number of neutron beam ports around the moderator and improve the efficiency for use of slow neutrons. For the coupled methane 9 moderator system equipped with the Be target, coupling effects of reflector materials (beryllium, lead and so on) and pre-moderator materials (water, mesitylene and so on) on the neutron intensity will be studied in detail.

2. Same Simulation Calculation for Mesitylene Moderators 3. Designing the Optimal Moderator System of a Coaxial Cylindrical Type Moderator

II-3.4. Results Obtained Till Now under the CRP

For the development of the compact and transportable neutron source for neutron scattering experiments, we have designed a cold neutron source equipped with a Li target and a proton linear accelerator with the proton energy of 2.5MeV and the beam current of 1mA. We 7 studied the neutronic performance of the Li (p, n) cold neutron source using the practical model in which the neutron absorption in the structure materials and the neutron streaming in the channels around the moderator were taken into account. The photons with energy of 7 14MeV or higher energy are produced in the Li (p, n) reaction and dominant surface photon 7 dose on the shielding components. However, the low neutron energies available from the Li (p, n) reaction may reduce the volume of shielding components. We thus separately designed the shielding components for neutrons and γ-rays to reduce the volume of the shield around 7 the Li (p, n) cold neutron source.

We obtained optimal dimensions of the moderator, pre-moderator and reflector so that the intensity of cold neutrons (E n<5meV) from the moderator is maximized. We estimated that 7 the Li (p, n) cold neutron source of 2.5 kW (E p=2.5MeV, I=1mA) yields the intensity of cold 2 neutrons (E n<5meV) of 2.4e4 [1/cm /s] at 5 meter distance from the moderator, which corresponds to that for the Bremsstrahlung (γ, n) cold neutron source of 0.8 kW (E e=35MeV, I=0.023mA).

We separately designed the shielding components for neutrons and γ-rays to reduce the 7 volume of the shield around the Li (p, n) cold neutron source. We aimed at reduction of the surface photon and neutron dose on the shielding components down to 10 µSv/h, respectively,

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since a 2.5MeV proton linear accelerator having the surface radiation dose of less than 20 µSv/h on the shielding components is permitted by the law in Japan to be transported for a use in a field. To achieve this, we found that we should use the lead slab of 12 cm thick and the slab of boric acid resin of 28 cm thick as the shielding component for γ-rays and neutrons, respectively. Finally, it was indicated that a compact neutron source system can be designed by using a Li(p,n) reaction although we need further information on γ-rays.

II-3.5. References

1. http://www.accsys.com/products/lansar.html 2. T. Tadokoro, et al ., “The Feasibility Study of the Boron Neutron Capture Therapy Using Proton Linac― Including the Isotope Generation for the PET Diagnosis―,” nd The 2 Meeting of Particle Accelerator Society of Japan (2005), [in Japanese] 3. C.L. Lee, X.-L. Zhou, Nucl. Instr. Meth. B 152, 1 (1999) 4. C.L. Lee et al, Med. Phys. 27, 1 (2000)

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II-4. R&D of productive pelletized cold neutron moderators

Kulikov Sergey, Bulavin M., Kulagin E., Shabalin D., Shabalin E., Verhoglyadov A. Joint Institute for Nuclear Research (JINR) Joliot-Curie 6, 141980 Dubna, Moscow region, Russia Fax: +7 (49621) 65-146; +7 (495) 632-78-80 e-mail: [email protected]

II-4.1. Short summary of work related to your agreement/contract performed in our group during the last 3-4 years

Solid methane neutron moderator (not pelletized but of integrity type) has been developed, fabricated (in 1999), and operated at the IBR-2 pulsed research reactor of the Laboratory of Neutron Physics (JINR). Its operation was unstable because of poor radiation resistance of methane. Then systematical experimental study of radiation effects in different materials potent for cold moderator were performed in 2000-2006, aiming to attain knowledge for reliable prediction of behaviour of hydrogenous compounds in advanced cold moderators of medium and high intense neutron sources. These works resulted in understanding that radiation effects in aromatic hydrocarbons are significantly less than in other substances studied.

Since then, R&D of new, pelletized type, solid aromatic hydrocarbons based cryogenic moderator began in the Cold Moderator Group of the Laboratory of Neutron Physics. In the frame of the work, comparative studies on structure and dynamics of materials - candidates for cold moderator were performed on the NERA inverted geometry spectrometer at the IBR- 2 reactor. It was shown that solutions of mesitylene (1,3,5 three-methylbenzene) with toluene, m-xylene and pseudocumene form glassy solids, and have relatively low barriers for methyl groups librations and additional density of states at low frequencies, which also makes these materials preferable as moderators for cold neutron sources.

Conceptional and technical design of the complex of neutron moderators for the modified IBR-2M reactor, including cold pelletized moderators with solid aromatic hydrocarbons glassy mixture, was accomplished in 2008. Optimal geometry and composition of moderators were found using Monte-Carlo simulation and experiments at the IBR-2 reactor. Technique of production of single round beads (balls) of solid aromatic hydrocarbons glassy mixture was derived, together with method of delivering beads into a moderator chamber by pneumoconveying . The last was studied both theoretically and experimentally at the room temperature mock-up.

II-4.2. Scientific scope of your project under the CRP

Scientific scope of our project under CRP covers cold neutron source physics, neutron moderation methods, cryogenic. Main goal of our project is to improve production of cold neutrons at the pulsed neutron source of Joint Institute for Nuclear Research – the research reactor IBR-2M. Conception of the productive pelletized cold neutron moderator is based on using small beads (balls) of frozen mixture of aromatic hydrocarbons (mesithylene, m- xylene). This enables long-run operation of cold moderator without replacement of the material or annealing as opposed to solid methane. Beads of mesithylene are conveyed to a moderator chamber with cold helium gas flow.

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Besides IBR-2M, such moderator of a novel type might be installed on others neutron sources, of medium or high power.

II-4.3. Detailed work plan for the next 18 months

II-4.3.1. July 2009 – December 2009:

Completion of construction of the full scale model of the technological system of the cryogenic moderator assigned to make testing of the main parameters of the moderator technology:

– manufacturing of mechanical parts of the model;

– elaboration of control and detection equipment, and system of collection and data presentation;

– adopting the helium cooler to the model;

– installation of the model;

– elaboration of an experimental programme.

II-4.3.2. January 2009 – March 2010:

Execution of the experimental programme at the full scale model of the technological system of the IBR-2M cryogenic moderator:

– Measurement of the technical characteristics of the helium blower;

– Measurement of heat load onto the cryogenic pipelines;

– Measurement of distribution of delivery time and velocity of mesitylene beads at the given parts of the conveying pipe and the moderator chamber at various conveying gas flow rate; processing of the experimental data and analysis, choice of acceptable gas flow rate providing integrity of the beads.

II-4.3.3. March 2010 – April 2010:

– Proceeding of execution of the experimental programme: pneumoconveying of mesithylene balls one by one at various input frequency – estimation of acceptable frequency of input balls into conveying pipe providing their uninterrupted charging into the chamber.

II-4.3.4. May 2010 – October 2010:

– Elaboration of an apparatus for neutron radiography of the cold moderator at the IBR- 2M.

II-4.3.5. Nov. 2010 – Dec. 2010:

– Preparation of a final report.

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II-4.4. The results obtained till now under the CRP

1. By computer simulation of gas flow with a separate ball inside cylindrical tube, characteristics of hydrodynamics at both stationary and non-stationary motion of a ball has been calculated. Both sliding and rolling type of movement were studied. Main result is that drag coefficient of a driving force is almost a linear function of a ball velocity.

2. To confirm and to make correction of the theoretical data, an experimental study of conveying of a ball along a cylindrical pipe has been performed. It appeared possible to make simulation of mesithylene beads transport by cooled helium gas with transportation of glass beads of the same size with flow of room temperature nitrogen. In the course of experimental programme, effect of bouncing of a ball when its speed exceeds 30% of the mean gas velocity, was discovered. Roughness of both walls of a conveying pipe and a ball itself is responsible for the effect.

3. Theory of transporting a ball with account for its bouncing was derived ; semi empirical factors of stochastic character of a ball motion in a cylindrical pipe was included into the transport equation.

4. By calculation, an acceptable parameters of safe conveying of mesithylene balls along cylindrical tube of complicated route with suitable mass flow was defined: conveying gas 3 temperature - 40 К, gas flow rate - 30 normal m /h (1.6 g/s), mean gas velocity in a conveying pipe of 16 mm diameter - 6 m/s.

5. A device for mesithylene balls preparation was fabricated and tested.

The device uses a principle of formation of a solid sphere of mesithylene and m-xylene mixture on the surface of liquid nitrogen. During freezing, droplet of mixture is held on the surface by vapour of boiling nitrogen. Then, after formation of solid round shell, it sinks down. Productivity of the device is two balls per second.

Diameter of solid balls is varied in the range 4.4– 4.8 mm. Up to the date, assembly and operational development of units of the device is completed: equipment for automatic maintenance of the constant level of mesithylene mixture and m-xylene (3:1) in the a metering tank, adjustable multichannel dropping bottle system, cryogenic part of the device with a separator for freezing and storage of solid balls.

6. Processing of experimental data on neutron moderation by mesitylene.

Experiments on passing monoenergetic ingoing neutrons in the range 10 – 100 meV through a cold mesithylene at 10 K, 3 0K and 50 K temperature were carried out in FLNP JINR at the IBR-2 reactor in 2006. In the frame of IAEA-JINR Contract, processing of these experimental data and Monte-Carlo simulation of the experiments were performed. Main results are as follows:

Temperature dependence of cold neutron flux (energy 1- 5 meV) at in the range 10-30K is as low as about 1% per 1K; in the range 30-50K – about 2%/K.

Monte-Carlo simulation using the MCNP code with available cross-section libraries for solid mesithylene created by Prof. R. Granada’s group showed that cold neutron spectra are in reasonable agreement with experiment for temperature 20-25K, except for the low edge of the spectrum 1 meV (20% of discrepancy). 73

7. Both conceptual and detailed design of a full scale model of the technological system of the cryogenic moderator was accomplished. The model is an exact copy of the camera of cryogenic moderator together with both cooling technology and a system for delivery of mesythelene balls to a moderator chamber (Fig 1-3). The only exception is a reactor itself. Existing helium cooler of 500 W, 15K supplies the model with 25-30 K helium gas which cools a conveying gas driven with a helium blower in the second coolant circuit. Passing balls through a pneumoconveying pipe is detected with an original method based on gas-dynamic effects. Filling a moderator chamber with balls is surveyed with a web- camera through quartz glasses.

Sure, gas flow rate, pressure and temperature of helium is detected as well. The fabrication of the model is in progress now.

5

4

3 2

1

Fig. 1. The main part of full scale model of technological system of cold moderators (1 – camera of cold moderator with vacuum shielding, 2 -thermal exchanger with helium blower, 3 - cryogenic pipes from/to helium cooler, 4 – place for charging device, 5 –transport tubes)

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Fig.2. Model of the cold moderator camera

Fig.3. Inner part of model of the cold moderator camera

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II-5. A Report on the feasibility of an ice Cold Neutron Source at Dhruva Reactor

Chief Scientific Investigator: Saibal Basu, Solid State Physics Division Bhabha Atomic Research Centre Mumbai 400085, INDIA

Other collaborators: Ramkrishna Das and Anil Kumar Sinha

II-5.1. Short Summery of work done during past four years

A suitably chosen cold moderator placed inside the reactor in a pre-decided location in a research reactor can shift the Maxwellian energy distribution of the neutrons to lower energies and can cause considerable enhancement in cold neutron flux. Broadly this is the underlying principle of a cold neutron source. Typically, neutrons with energy less than 5 meV or wavelength more than 4 Å are termed as cold neutrons. Experiments performed in 1960’s clearly demonstrated suitability of D 2O ice as cold moderator. Ice-based moderator is not hazardous and may be an attractive option. With this background, we felt that a H 2O ice based source maintained at cryogenic temperature using liquid nitrogen as coolant is worth considering for implementation at Dhruva reactor in Trombay, India. At this temperature water becomes polycrystalline ice Ih. This phase of ice is expected to give good moderation because it has six translational modes at 7.1 meV, 13.2 meV, 19.0 meV, 24.2 meV, 28.2 meV and 37.7 meV; while libration, bending and stretching modes exist at 89 meV, 204 meV and 406 meV respectively. To confirm that H 2O ice can indeed shift the thermal spectrum to lower temperature, first an experiment was carried out in APSARA reactor to measure the from an ice moderator. This was followed by a mock up test where a test loop was built to form and maintain ice at 100K using liquid nitrogen flow under simulated nuclear heating corresponding to heat load at Dhruva reactor operating at 100 MW (thermal). A moderator pot for efficiently producing ice in-situ was designed and fabricated for the first experiment in APSARA reactor. The moderator pot was made from pure aluminium in cylindrical geometry. Diameter of the cylindrical moderator pot was about 200 mm and the 3 thickness of the pot was about 50 mm. It could hold approximately 600 cm of water in it. The pot was radially separated into two chambers: the central chamber was meant for holding water and the peripheral chamber was for circulating LN 2 to cool the water chamber. Efficient cooling of moderator depends on the design of the moderator pot. It is well-known that ice is an inefficient conductor of heat. Once ice starts forming at the periphery of the moderator pot, it would have been a slow cooling for the central region of the cylindrical moderator pot. To overcome this problem, two equally spaced aluminium plates of 1 mm thickness were welded peripherally inside the LN 2 chamber, separating the thickness of the cylinder in three compartments. These plates were perforated, so that the entire moderator chamber formed a single volume for water. They allowed extremely efficient cooling of water in the entire volume of the cylinder, though liquid nitrogen flowed at the periphery only. The pot also had water inlet and a central hole to allow expansion of water during ice formation, so that no stress developed at the welded joints. A chromel-alumel thermocouple was inserted in the moderator chamber near the centre, to monitor the cooling rate and the ultimate physical temperature attained in water by flowing LN 2 through the moderator pot, after filling the moderator chamber with water. For flowing LN 2 through the nitrogen chamber, two pressurized LN 2 Dewars were used. By controlled pressurization of one Dewar, we could

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transfer LN 2 from one Dewar to the other through the moderator pot’s nitrogen chamber at any desirable rate. Before proceeding with the experiment at APSARA, several trial runs were made to determine the cooling rate and the ultimate temperature of the ice moderator in the moderator chamber. We found that it took approximately twenty minutes to reach the o lowest temperature of approximately –193 C (80K) as recorded at the centre of the chamber by the chromel-alumel thermocouple. In all the cooling experiments, the moderator pot was covered by thermocol for thermal insulation. For such short runs this insulation was adequate and it also prevented any condensation outside the moderator pot. To get details of the Maxwellian emanating from a cold moderator and to compare its gain with respect to the room temperature moderator, one needs to measure the intensity as a function of energy at both the temperatures. Instead of this, one may also estimate the cold spectrum by measuring the integrated intensity of a Be-filtered beam. Be is an excellent filter for removing neutrons of energy more than 5 meV, allowing only cold neutrons to pass. A Be-filtered beam gives a good indication of integrated fraction of cold neutrons in the incident spectrum. The experiment consisted of starting with the Be-filtered neutron counts in a detector for the water moderator at room temperature and then collecting neutron counts after removing the Be filters from the beam. Difference between these two counts gave the number of neutrons below Be cut off energy. This subtraction also removed the background counts at the detector from all possible sources. We observed that the background was quite large for the current position and this method was most effective to remove background counts. The abovementioned difference count was used to obtain the number of counts below Be cut off, which is theoretically 1.6% of the total area under a room temperature Maxwellian. Next the Be filters were placed in front of the detector and the moderator was cooled by flowing liquid nitrogen. While the moderator started cooling down to form ice, the count in the Be-filtered beam went up, due to the lowering of the neutron temperature. We waited till the lowest temperature of the moderator was reached and then the counts were recorded. The increase in the counts of Be-filtered neutron beam coming from the cold moderator with respect to the counts from room temperature moderator indicated shift in the Maxwellian to lower temperature. Subtracting the room temperature counts below Be cut off, we obtained the counts, solely due to lowering of the temperature of the neutron spectrum emanating from the cold moderator. This count was compared with the number we obtained from room temperature moderator, below Be cut off. The ratio of these two counts was used to estimate the temperature of the cold neutrons and the expected gain from an H 2O ice moderator at about 90K. We estimated a neutron temperature close to 100K from this experiment. The experiment clearly demonstrated that H 2O ice cooled by liquid nitrogen is a good and inexpensive cold moderator, which can be implemented either in a reactor or along with an accelerator based neutron source. This source will also be safe to handle compared to hydrogen or hydrocarbon-based sources. Based on this experiment a detailed Mock Up test was carried out for formation and maintenance of ice under simulated nuclear heating. The Mock Up test was also used to formulate a general design principle of safe operation of an ice source in a reactor.

In general the broad targets of the mock-up test were the following.

– To design a Moderator pot and to test it in order to validate its design concept.

– To monitor and determine the cooling down period (to bring down the temp. of Moderator from ambient temp. to around 80K to 100K range, at various reactor power levels, simulated by varying the heat load (on the Moderator) by an external electrical heater.

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– To determine the minimum flow rate of LN 2 (Liquid Nitrogen) for maintaining the desired Moderator temperature (as close to 100K as possible). A flow rate of 0.5 LPM had been estimated to remove the radiation heat load of approximately 1 KW. The heat load in the moderator pot and the moderator will be approximately 880 W when the Dhruva reactor operates at 100 MW power level. – To verify, whether the flow rate of LN 2 (obtained as above) is sufficient for achieving the required 80K to 100K Moderator temperature range. Based on the data acquired in the short duration tests, we could estimate the LN 2 consumption per day and the feasibility of operating / maintaining the (LN 2) cryogenic flow loop.

– To observe temperature rise (of the moderator) V/s time, for a given level / heat load, after the cooling by LN 2 is stopped. This has importance from the point of design of control systems for safe operation of the Cold Neutron Source.

– In general, to test the low temperature compatibility of the whole set up. To observe temperatures (frosting) at various joints and connections, and their effect on several critical components, under various flow conditions of LN 2.

We propose to run the cold source with stored supply of LN 2, so that we don’t need to maintain and operate any LN 2 plant near the reactor. The flow loop in the Mock Up experiment primarily consisted of two LN 2 Dewars: an inlet Dewar from which saturated LN 2 was circulated to the moderator pot and an outlet Dewar which collected the liquid-vapour mixture of nitrogen at about atmospheric pressure. LN 2 flowed to the moderator pot when inlet Dewar was pressurized with nitrogen gas. During cryogenic operation the moderator pot had to be thermally isolated. This was done by placing it inside a vacuum jacket. The Moderator pot was supported on two legs (having ball and socket type spacers). The legs kept the Moderator pot at the centre of the water cooled vacuum jacket, thus ensuring minimal -5 external thermal load. The vacuum jacket was evacuated to ~10 mbar pressure before we started cooling the water by LN 2. The tubes carrying liquid nitrogen to and from the moderator pot were made of Aluminium towards the side of the moderator pot and made of SS304 outwards. We had designed double-walled transfer lines for carrying LN 2 up to the vacuum jacket flange. The lines were connected to the LN 2 carrying lines inside the vacuum jacket through a bayonet type joint. This minimized heat transfer from ambient to the moderator pot. Outside the vacuum jacket liquid nitrogen flow occurred through rigid (vacuum insulated) transfer lines. These lines had bayonet type joints on both ends. In the absence of LN 2 circulation, nuclear heat in the moderator pot assembly will be removed by circulating water through Moderator pot, without disturbing the vacuum in the jacket. If we start with the ice at temperature close to 100K, and if at any time there is a failure of LN 2 0 flow, then after a certain period the ice will melt on crossing temperature of 0 C. Once this happens, flow of water should extract the nuclear heat from the Moderator pot. In this regard the time it takes for the ice to melt is an important parameter for the design of the control system. We have monitored this time interval under various nuclear heating conditions simulated by the electrical heater. Also, required water flow rates to maintain the moderator pot close to room temperature have been recorded for different nuclear heating rates. The inlet line has a vertical riser. During freezing of water in the moderator pot, water expands and comes out through inlet line. We had provided this riser so that we could indeed see that the water is coming out from the inlet. In case of emergency when there is no liquid nitrogen or water circulation the moderator will be cooled by pressurizing the vacuum jacket with helium gas for conducting nuclear heat out to the vacuum jacket. The general operating principles of the cold source envisaged by us have been vindicated by the Mock Up test. 79

II-5.2. Scope under the present CRP

The present CRP targets production and utilization of short pulsed cold neutrons for accelerator based neutron sources. Production of cold neutrons, either in a reactor or in an accelerator based spallation neutron source follows same principles and the moderators used for re-thermalization are also similar. Water at ambient temperature is already used as a source of thermal neutrons at the spallation neutron source in ISIS, UK. There have also been experiments that suggest that H 2O ice at 10 K is a suitable moderator for production of cold neutrons. At the moment we are pursuing the design and installation of an ice based cold neutron source for a specific beam hole in the reactor DHRUVA at Trombay India. As described earlier, we had already progressed in this direction since the experiment at APSARA for determining neutron temperature, before we joined the CRP. The present CRP has provided the forum for sharing our experience on development of such a safe and inexpensive water based cold source which can be implemented in a reactor or an accelerator based source. Through the CRP we have also started collaboration with Ronaldo Granada of Argentina for optimizing the geometry of the ice moderator at Dhruva by Monte Carlo Simulation. The scattering kernel has been provided by Granada using a synthetic model for scattering from ice at 100K proposed by him. This simulation will decide the final geometry of the moderator pot at Dhruva.

II-5.3. Results obtained under the CRP

Since the first RCM at Hokkaido, Japan, we had completed the mock up test for the proposed flow loop and the set up under simulated nuclear heating, while ice was formed and -5 maintained under a vacuum of ~10 tor. The following conclusions were drawn based on the experiment.

0 – The temperature at the centre of the moderator will be approximately -144 C or 130K, when the reactor operates at 90 MW. As the cooling was done from the periphery and the heater was fixed at the centre of the Moderator pot, the temperature at the centre of the pot was the highest possible temperature of the moderator. In case of uniform heating (in the reactor) of the moderator and moderator pot the temperature at the centre of the pot should be lower than that obtained in the tests. For a reactor power level of 60 MW (heat absorbed by the moderator will be 530 W. The temperature at the centre was 0 0 between -168 C and -162 C (105K – 111K). The temperature at the periphery of the pot 0 0 remained between -186 C and -181 C (87K to 92K) for all the heater power levels. The temperature distribution in the entire volume of moderator will remain in the range of 90K to 130K depending on the reactor power level. Better uniformity of temperature is expected in the case of uniform nuclear heating, compared to local electrical heating that had to be done in the case of mock-up tests.

– The highest heater power level in the present set of experiments (1400 W) corresponded to 800 W heat delivered to the Moderator pot. This is close to the reactor operating at full power. At this power level a LN 2 flow rate of 0.5 kg/min was sufficient to maintain the temperature at equilibrium. The stability of the temperatures measured inside the moderator and on the body was checked for more than an hour. At this power level LN 2 loss rate was 0.4 kg/min. This loss rate corresponds to about 700 Liters of LN 2 per day. For a reactor power of 60 MW, the nuclear heat will be about 530 W on the Moderator pot. At this nuclear heating rate the loss rate of LN 2 was about 0.25 Kg/min. This loss rate corresponds to 450 Liters of LN 2 per day. The daily consumption of LN 2 will lie between 500 Liters to 700 Liters, depending on the reactor power level.

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– The LN 2 supply was switched off at heater power level of 1200 W and 1400 W several times, allowing the moderator to heat up with vacuum maintained in the vacuum jacket. This was done to simulate the los of coolant to the ice moderator during reactor operation. It takes nearly 30 minutes for the moderator to cross 0ºC temperature level under the vacuum conditions. The water flow through the Moderator pot started on its own, once the ice melted . A nominal water flow rate of 1 LPM will maintain a temperature difference of approximately 11ºC between inlet and outlet of water at reactor full power operation. This flow rate will be sufficient to maintain the moderator at an acceptable temperature, even when LN 2 supply stops / does not exist. The vacuum in the jacket need not be disturbed for heat removal from Moderator pot.

– The cool down time, with the heater power on, was 110 minutes for heater power level of 1400 W. This is equivalent to starting the Cold Neutron Source operation with the reactor powers at 90 MW. The results show that we will be able to start the Cold Neutron Source operations, with the reactor in full power and the moderator will cool down to its equilibrium temperature in approximately 2 hrs time.

In general, the results of the present series of tests performed under simulated nuclear heating by electrical heater, on the prototype ice moderator (under vacuum), indicates that the moderator will have an equilibrium temperature distribution in the range of 90 K to 140 K in its entire volume, depending on the reactor power level. As the heating was localized in the case of mock-up tests, unlike nuclear heating in actual case inside the reactor, it is expected that there will be better uniformity of temperature of the moderator inside the reactor for ice based Cold Neutron Source. An inventory of about 700 Litres of LN 2 per day will be sufficient to operate the Cold Neutron Source, even with full power reactor operation. A nominal flow rate of 0.5 kg/min (0.6 LPM) of LN 2 will be sufficient to remove the nuclear heat from the moderator. This can be easily achieved by pressurized flow from a source Dewar. In case of loss of LN 2 cooling, we confirmed that water flow starts automatically after the ice melts, if the water line is kept connected to the moderator pot. Once the ice melts, a water flow of 1 LPM will keep the Moderator pot temperature within acceptable limits, without disturbing the vacuum in the vacuum jacket.

For the Mock up test design of the moderator pot was such that the cooling occurs from the periphery and water was allowed to escape from a centrally placed tube to accommodate the expansion of water at the time of ice formation. We found out after the Mock up test that there was bulging of the moderator pot due to thermal cycling. This observation points to the possibility of water pockets getting trapped inside the moderator pot during freezing. To address this issue we have started detailed design and simulation of the cooling process in the moderator pot, using finite element technique, before we fabricate the final moderator pot. The moderator pot will be made from Al-Mg alloy 5154.

II-5.4. Detailed work plan for next 18 months

– Complete Monte Carlo simulation process for obtaining the optimized geometry of the moderator pot: As described earlier, we have undertaken optimization of the moderator geometry for best possible output of cold neutrons from the ice moderator. We have already got the preliminary results for the ice cold source located at beam hole CS 3003 in Dhruva. This is a dedicated beam hole for the cold source. The input spectrum for the cold source is known for this location and that has been used in the Monte Carlo

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program. We are optimizing the thickness of the moderator at the abovementioned location for an ice temperature of 100K.

– Complete the engineering design of the moderator pot using finite element techniques for simulating the ice formation process, so that no water can remain trapped in the moderator pot at the time of ice formation. Otherwise there will be large stress developed in the moderator pot, every time ice is formed and the moderator pot will fail eventually.

– Prepare a complete flow diagram (based on the experience of Mock Up test) and a fail- safe control logic for operation of the cold source.

– Prepare a complete safety report for the installation of the cold source. This safety report will contain design of various components, based on our tests and simulation results. The safety report will be submitted for evaluation and needs to be cleared before we attempt installation of the cold source in the reactor.

– Design the shielding for the specified beam hole and get it cleared by safety committee and then fabricate the same. – Procure and install LN 2 dewars in the vicinity of the reactor hall of Dhruva. Arrange laying of cryogenic lines to the beam hole mouth for cold source.

– Assemble the components of the in-pile assembly inside the vacuum jacket and test.

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ANNEX III. ENERGY-DISPERSIVE TRANSMISSION MEASUREMENTS

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III-1. Development of high resolution transmission method

Yoshiaki Kiyanagi*, Takashi Kamiyama, Fujio Hiraga and Michihiro Furusaka

Division of Quantum Science and Engineering, Graduate School of Engineering, Hokkaido University, Kita-13, Nishi-8, Kita-ku, Sapporo 060-8628, Japan

* Contact person, Fax. +81-11-706-7368, E-mail: [email protected]

III-1.1. Short summary of work related to your agreement/contract performed in your institute during the last 3-4 years

III-1.1.1. Residual strain measurement and mapping of residual strain by Bragg edge transmission

Neutron diffraction has been used as non-destructive tests for materials and has played an important role in the determination of residual strains in materials, vehicle engines, gas turbine engines and welding ducts, etc . Neutron radiography using a pulsed source also has proven to be a useful tool for the non-destructive test. The transmission spectrum through a sample displays a well-defined increase in intensity with neutron wavelength and exhibits a step-like decrease, so called Bragg-edge. The Bragg-edges occur because for a given hkl reflection, the Bragg angle increases as the wavelength increases until 2 θ = 180°. Bragg-edge transmission has unique advantages over conventional neutron diffraction: (i) detecting the total cross section and (ii) mapping of strain using a 2d position sensitive detector.

We tried to analyze the residual strain and mapping of residual strain in Fe plate. A 2d position sensitive detector consists of 8 × 8 Li-glass scintillator with a size of 1.7 mm × 1.7 mm. The detected area is about 20 mm × 20 mm. The size of Fe plate is 100 mm × 50 mm × 5 mm. Fig. 1 shows the detected area and Bragg edge pattern of Fe plate. We focus on the change of Bragg edge profile in a wavelength region 3-4.2 Å. It is thought that the residual strain is influenced appreciably because (110) is closed-packed lattice plane in the bcc structure.

30 3 non strain 3 strain 1 2 3 4 5 6 7 8 Lane 25 110

20

1 2 3 4 5 6 7 8 211 200 220 15 310 9 10 11 12 13 14 15 16 10

Total section (barn) cross 5

17 18 19 20 21 22 23 24 0 1 2 3 4 5 wavelength (Å) 25 26 27 28 29 30 31 32

30 6 non strain 33 34 35 36 37 38 39 40 6 strain 25

20 200 110 41 42 43 44 45 46 47 48 211 220 15 310

10 49 50 51 52 53 54 55 56 Total cross section (barn) section Total cross 5

0 57 58 59 60 61 62 63 64 1 2 3 4 5 wavelength (Å)

64 pixels

Fig. 1 The detected area and Bragg edge pattern of strain Fe and non-strain Fe.

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The total cross section of the strain sample is larger than the non-strain sample, which means that the number of transmitted neutron of the strain sample is smaller than that of the non- strain sample. The Bragg-edge positions of the strain sample correspond to non-strain one, which means that their crystal structure does not change by applying a load. The Bragg edge profile of strain sample becomes broad in comparison with the non-strain sample. The broadening profile of the strain sample in a wavelength region 3-4.2 Å shows the different orientations of crystallites. The texture can have a marked effect on the overall shape of the Bragg edge profiles recorded for each hkl reflection. Table 1 shows the residual strain at each hkl reflections and lanes. The residual strain is defined by following equation:

1 0 0 εhkl = ( d hkl – d hkl ) / d hkl ×100,

0 1 where εhkl is residual strain (%), d hkl is lattice spacing of the non-strain sample and d hkl is lattice spacing of the strain sample.

Table 1 The residual strain of the strain sample at each hkl reflection and lane. (%)

hkl / lane 1 2 3 4 5 6 7 8

431 0.07 0.01 -0.10 -0.05 0.04 0.05 -0.01 0.08

330 0.09 0.03 0.08 0.09 0.04 -0.04 -0.10 -0.01

321 0.01 -0.08 -0.02 0.02 -0.07 0.02 0.01 0.00

222 0.02 0.00 -0.01 0.01 0.04 -0.07 0.02 0.02

310 0.01 -0.08 0.01 -0.01 0.00 -0.04 0.04 0.00

220 0.05 -0.03 -0.13 -0.07 0.04 -0.11 0.02 -0.02

211 -0.07 0.00 0.00 -0.07 -0.06 -0.07 -0.09 -0.07

200 0.00 -0.04 0.12 -0.01 0.01 -0.02 0.11 -0.01

The residual strain shows the large difference value at every lanes, and maximum and minimum strain reach 0.13% and 0.00%, respectively. It is clarified that the distribution of compressive strain and tensile strain exist at several points and complex defects are formed into the material by plastic deformation. Thus, Bragg edge transmission method can detect the residual strains as well as complex distribution using a 2d position sensitive detector with high counting rate.

III-1.1.2. Observation of crystal structure and texture change

The Bragg edge transmission method gives information on crystal structure. So, we can get information of re-crystallization and crystal growth. We observed position dependent crystal growth of Pb, which indicated that single crystal phases appeared and the variation of the crystal structure existed depending on the position in the sample.

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III-1.2. Scientific scope of your project under the CRP

The transmission method using the pulsed neutron source will give much more informative data than the traditional neutron radiography. The total cross section near the Bragg edge may includes many kinds of structural information, for example, crystal structure, crystalline size and its orientation, lattice plane distribution, change of lattice spacing and so on. Some of such information probably cannot be obtained easily by a diffraction method. Therefore, this method has possibility to be very useful and compendious to examine the material structures and textures.

The detector development is another important issue, and this development is useful not only for this method but also for other neutron scattering experiments.

III-1.3. Detailed work plan for the next 18 month

III-1.3.1. Model experiments to verify the reliability of the transmission method

We are developing a new data analysis code for the transmission method to get the information of crystal structure and texture. To verify the validity of the code, experiments of in-situ strain measurements will be performed by using both methods of the transmission and the diffraction.

III-1.3.2. Simulation for studying the optimal condition of the experimental setup for the transmission method

The transmission spectra are affected by the multiple scattering and sometimes the small angle scattering. To assess the effect of the multiple scattering and beam divergence is important to perform the data analysis for the precise information on preferred orientation, strain distribution and so on. We are developing a simulation code that can simulate the inelastic and the elastic scattering in the forward direction. We will complete the code development and perform the calculations to know the multiple-scattering effect including the beam divergence on the transmission spectrum and finally get the optimal condition of the experimental setup.

III-1.3.3. Detailed observation on a welded sample

We will investigate in more detail the texture and the residual strain in the steel welding material. Welding material consists of parent material, welded place and heat affected zone (HAZ). The texture can have a marked effect on the overall shape of the Bragg edge profiles recorded for each hkl reflection. From the change of shape of Bragg edge profile, welded material may be divided into parent material, welded place and HAZ. In order to understand the detailed mechanism of a fatigue failure of welding material, we will try to specify the positions of parent material, welded place and HAZ and determine the residual strain quantitatively at different texture by one measurement.

III-1.3.4. Effect of the crystalline size on the transmission cross section

Grain size affects the total cross section of the crystalline materials. We have already measured transmission spectra of two SS samples having different grain sizes. It was observed that the transmission cross section of the large grain size sample was smaller than that of the smaller sample. However, the method to evaluate the grain size effect has not been accomplished. We will proceed the study on the grain size effect. 87

III-1.3.5. Experiments on practical materials

In order to evaluate the effectiveness of high resolution transmission measurements, some experiments on the practical materials will be performed.

III-1.3.6. Detector development

We are now developing a GEM detector with KEK and application of a colour imaging intensifier (Colour I.I.) to the time-of-flight method with Toshiba co. We will improve the detection efficiency of the GEM detector and apply Colour I.I. for the precise measurement of time-of-flight spectroscopy.

III-1.4. The results obtained till now

III-1.4.1. Imaging of texture information obtained by transmission spectra analysis

We obtained the images of an unbended iron sample and a welded SS sample. The transmission cross section at each pixel was analyzed by using a code newly developed. For both samples, images of preferred orientation were clearly shown. The results indicate that the transmission spectroscopic imaging can give spatial dependent information of texture. The new data analysis code is indispensable for the transmission method to get the information of crystal structure and texture. However, the code is still in a developing state. Verification of the code is necessary.

III-1.4.2. Simulation for studying the optimal condition of the experimental setup for the transmission method

In the code of MCNP a scattering to forward direction is not usually correctly treated. Therefore, we revised the Phits code to have a capability of calculation for forward direction scatterings. By using this code we can get transmission spectrum of crystalline materials, and also forward scatterings by hydrogenous materials. Further development for more detailed calculation is now under progress. By using this code we will perform the simulation calculation to know the effect of multiple scatterings and beam divergence on the transmission cross section.

III-1.4.3. Observation of re-crystallization of Pb-Bi eutectic

Pb-Bi is a candidate for a target and a coolant of an accelerator driven system. After solidification the volume expands, which may cause serious problems such as rupture of the pipes. The expansion phenomenon was studied by various methods (1-3). The reason of expansion is re-crystallization of γ phase as indicated by X-ray diffraction (1). We observed a growth of γ phase and spatial distribution of γ phase in the solid samples prepared under different cooling speeds. The results showed that the rapidly cooled sample had more homogenous distribution of the crystal structure than the slowly cooled one. Faster re- crystallization was observed in the rapidly cooled sample than the slowly cooled one. It was demonstrated that the transmission spectroscopic method was a powerful tool for looking at the spatial distribution of structure in the heavy metal materials.

III-1.4.4. Effect of the crystalline size on the transmission cross section

Grain size affects the total cross section of the crystalline materials. We consider that the large grain size causes reduction of the transmission cross section due to the extinction effect. 88

Transmission spectra of two SS samples having different grain sizes were obtained. It was confirmed that the transmission cross section of the large grain size sample was smaller than that of the smaller grain size sample. We need further experiments using different grain size samples to get quantitative data on the grain size.

III-1.4.5. Detector development

We performed transmission measurements by using a GEM detector developed by KEK. We examined the spatial resolution and detection efficiency. The spatial resolution is about 2 expected one, less than 1 mm , and the efficiency is about 30%. The detector was also used to get transmission images of a welded iron sample. Furthermore, a colour imaging intensifier (Color I.I.) was also examined with Toshiba co. By adopting a rough time-of-flight measurement, we can distinguish the image of γ rays from the neutrons, and also different kind images corresponding to different neutron energy range.

III-1.5. References

(1) H. Glasbrenner, F. Gröschel, H. Grimmer, J. Patorski, M. Rohde, Journal of Nuclear Materials 343 (2005) 341-348 (2) P. Agostini, E. Baicchi, A.Zucchini, G. Benamati, Journal of Nuclear Materials 335 (2004) 275-279 (3) A. Zucchini, P. Agostini, E. Baicchi, Journal of Nuclear Materials 336 (2005) 291-298

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III-2. Bragg edge transmission analysis at a medium intensity pulsed neutron source

Chief Scientific Investigator: José Rolando GRANADA

Scientific Investigator: Javier Roberto SANTISTEBAN

Collaborators: Javier DAWIDOWSKI, Florencia CANTARGI, Aureliano TARTAGLIONE, Sergio PETRIW, Jerónimo BLOSTEIN, Luis CAPARARO

Centro Atómico Bariloche

Comisión Nacional de Energía Atómica (CNEA)

ARGENTINA

III-2.1. Short Summary of Work related to this Contract

The technique of Bragg-Edge Transmission (BET) analysis exploits the sharp edges appearing in the neutron total cross section (and hence in the transmission) of polycrystalline materials. These edges occur because, for a given hkl reflection, the Bragg angle increases as the wavelength increases until 2 θ is equal to 180°. At wavelengths greater than this critical value no scattering by this particular {hkl} family can occur, and there is thus an increase in transmitted intensity. BET provides standard crystallographic information about a sample, so it has been used in material science studies for quantitative phase analysis [1] and for the definition of applied and internal stresses [2]. Fast count rates and a good signal-to-noise ratio can be achieved by using relatively thick specimens without affecting the d-spacing resolution, turning BET into an attractive technique for low-intensity pulsed sources based on small accelerators, such as the 25 MeV electron LINAC existing at our laboratory.

Phase analysis studies are based on determinations of the height of the Bragg edges, whilst in stress analysis the information is obtained by detecting very small changes in the position of the edges as the sample is tilted in the neutron beam. As we wish to implement the technique of BET analysis at our laboratory, we have produced figures-of-merit for the determination of the height and position of the Bragg edges, which include the most relevant experimental parameters [3]. Within this framework, during the past two years we have been carrying on a steady instrumental program aimed at furnishing our laboratory with a new and versatile cold moderator, together with a beamline specifically dedicated to transmission experiments in the thermal and subthermal ranges. The progresses achieved within this area are reported later in this work.

Despite its apparent simplicity, a reliable analysis of the transmitted signal is many times prevented by the presence of preferred orientation or texture , which distorts the intensity and shape of the transmitted neutron spectra from the simple behaviour observed for isotropic specimens. An example of this is made clear in Figure 1, which displays the total cross section along three directions of a rolled AA7150 aluminium plate, measured by us at ISIS, UK. Due to this anisotropy in the total cross section, the wavelength-dependant neutron transmission of the sample is different along different directions [4]. Rather than a drawback for the BET technique, these observations have opened the prospect of using neutron transmission experiments for the characterization of crystallographic textures; provided many materials are polycrystals with a non-random distribution of orientations. Moreover, because in most manmade objects such orientation distributions are not homogenous across the object,

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it has been quickly realized that the neutrons transmitted through an object can reveal local variations in crystallographic texture.

8.75 Along ND 7.50 Along TD Intermediate direction 6.25 Isotropic

5.00

3.75

2.50 Total cross section (barns) 1.25 (220) (311) (200) (111) 0.00 2 3 4 5 Neutron wavelength (Å)

Figure 1 : Total cross section of a rolled AA7150 aluminium plate along different directions compared to prediction for an isotropic specimen.

Teamed with a group with long expertise in neutron radiography, we have recently demonstrated that it is possible to produce neutrographs of the “texture variations” across a sample (Figure 2), by selecting the energy of the neutrons produced by a pulsed source [5].

Figure 2 : Radiographic transmission images of a steel welding (picture, right) as a function of neutron energies.

Using a different technology, the imaging of texture variations across samples has also been achieved by other participants of the present CRP [6]. Such energy-selective imaging instruments have already been proposed for the major spallation neutron sources [7], showing the current interest existing in this area of research. An understanding of the connection between crystallographic texture and the changes observed in the transmitted intensity is the present challenge for a proper interpretation and quantification of such images.

The determination of texture-induced changes in the neutron total cross section (as those seen in Figure 1) is experimentally much easier than the precise determination of the height and position of the Bragg edges. So, such studies can be performed effectively at medium intensity pulsed sources of moderate resolution. The prediction and analysis of the total cross section of textured materials can be cumbersome to start with, but if effectively implemented it could provide a very useful tool for material science research. Details of the work performed on this subject under this CRP are presented later in this report. 92

III-2.2. Scientific Scope of our Project under this CRP

As stated in our original proposal, the overall objectives of our Project are:

1- To implement the technique of Bragg edge neutron transmission analysis at a medium-intensity pulsed neutron source, namely the 25 MeV LINAC at the Neutron Physics Laboratory, Centro Atómico Bariloche, Argentina.

2- The development and maintenance of a freely-distributable computer code for least- squares analysis of Bragg edge transmission experiments mostly oriented towards medium intensity neutron sources.

In view of recent developments within the area of Bragg Edge Transmission analysis (as reported in the previous section), we consider that it would be worth and timely to dedicate part of the future research effort and programming effort to the topic of Texture analysis by Bragg edge transmission experiments . Details of the proposed work plan are given below.

III-2.3. Detailed Work Plan for the next 18 months

III-2.3.1. Implementation of Bragg edge transmission beamline at the Bariloche LINAC

We are interested in performing Bragg edge experiments on relatively small samples (e.g., on a tensile test specimen); or on a small sections of a larger sample (e.g., a region near a weld). So we plan to optimize the neutron optics and the detector size and position for such studies.

We do not have a neutron beam monitor in our transmission beamline, so we have traditionally normalized our transmission experiments by using the “sample in-sample out” technique, which demands long counting times for the open beam. We wish to install a neutron beam monitor on the Bragg edge transmission applications in order to reduce the experimental times dedicated to measure the open beam.

Besides this we have recently finished the construction of the moderator recipient and cryogenic vessel, so the tasks we propose within this topic are:

- Commissioning of the recently-built cold moderator and associated cryogenic device.

- Installation of a new neutron beam monitor for this beamline.

- Installation of a transmission detection bank optimized for studying small samples.

- Implementation of Nexus-compatible file formats within the data acquisition software (see section below).

III-2.3.2. Development of a Bragg edge computer code

As stated in the original research contract, we intend to produce a Bragg edge analysis package able to be transported to other research centers. So, in order to standardize the package we have decided to adopt Nexus, a data format specially designed for neutrons and X-ray experiments (www.nexus.org), which is becoming increasingly popular across neutron facilities. The adoption of such a standard will ensure the portability of code written by different research groups.

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Besides this, we have observed an increasing application of Bragg edge analysis to 2D mapping/radiography, so we have decided to produce a version of the Bragg edge fitting routines for Matlab™, a very popular computer package widely used for 2D mapping, analysis and visualization. Also, as explained above, we have decided to dedicate part of our effort to producing a code for the analysis of textured materials.

So, the tasks we propose are:

- Definition of input/output routines using the Nexus format

- Definition of a “TOF transmission” instrument within the Nexus format.

- Creation of a Matlab library for single-Bragg edge fitting analysis.

- Creation of a Matlab library for the calculation of total cross section of textured materials.

- Publication of the software via a dedicated webpage

III-2.4. Results obtained under this CRP:

III-2.4.1. Implementation of Bragg edge transmission beamline at the Bariloche LINAC

Our pulsed neutron source is based on a 25 MeV electron LINAC, which produces photoneutrons after being stopped on a lead target. The source can be operated at 12.5, 25, 50 3 and 100 Hz, with varying electron current. The detection bank, consisting or one or more He detectors, can be placed at 3, 8 or 17 metres from the target. So, the source pulse rate and the neutron flight path can be tailored to accommodate the wavelength where the first Bragg edge appears. For biological shielding, the lead target sits within a container having a water-filled double wall surrounded by cadmium cladding, see Figure 3-(a).

Figure 3. Details of the new moderator design and the associated liquid nitrogen cryostat.

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Figure 4. (a) Source-premoderator-moderator system used in Monte Carlo simulations (b) Neutron flux density at the moderator face (c) Emission time of neutrons with wavelengths between 3 and 8Å

5

Along TD 4 Along ND Isotropic 3

2

1 Total elastci cross section (barns) (311) 0 (200) (220) (111)

2 3 4 5 Neutron wavelength (Å)

Figure 5 : Calculated total elastic cross section of a rolled AA7150 aluminium plate along two different directions compared to prediction for an isotropic specimen.

We have designed and built a novel and flexible moderator with a low maintenance cost, in order to optimize neutron production for neutron wavelengths of interest to Bragg edge transmission experiments (3Å and 8Å). This ‘cool’, i.e., not so cold, moderator consists of a two-chamber Zircaloy-4 container refrigerated by a liquid-nitrogen cryostat, has been specially designed to fit close to the target, within the recipient used for biological shielding. The Zircaloy-4 container can be filled in with a moderator material that is liquid at room temperature (water, benzene, mesythylene, etc). For a more efficient thermalization process, a pre-moderator at room-temperature sits between the moderator and the lead target, outside the liquid nitrogen cryostat. The pre-moderator, typically consisting of a polyethylene slab, can be coupled or decoupled from the moderator by a cadmium sheet. The pre-moderator thickness can be easily targeted to the experimental needs. Figure 3-(c) shows the stainless steel cryostat, presently being tested in order to be commissioned.

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The selection of moderator and premoderator materials and the optimization of its dimensions are performed through Monte Carlo simulations of the thermalization process in the source- moderator–premoderator system. Many different scenarios were evaluated in a Ph D Thesis developed within our group using the code MCNP [8]. Figure 4-(a) shows a typical model for the simulations, where the different materials are identified by different colours. The most interesting quantities resulting from the simulations are the neutron flux at the moderator face n0, and the neutron pulse width µ for selected neutron wavelengths, which dictate the count rate and the resolution of the transmission experiments respectively. Figure 4-(b) show the results of n0 for simulations using benzene at room temperature as moderator, and a polyethylene slab of different thicknesses as premoderator. The figure corresponds to the decoupled case, with a cadmium sheet between premoderator and the cryostat vessel. Figure 4-(c) shows the distribution of the time of emission of the neutrons from the moderator face, from which it is possible to estimate the pulse width µ. The simulations have been validated and refined by experimental tests. So far, the optimal configuration for typical Bragg edge transmission experiments consists of a mesythylene moderator at liquid nitrogen temperature, and a 24mm thick polyethylene premoderator.

III-2.4.2. Development of a computer code for Bragg edge analysis

So far, there are two successful applications of Bragg edge transmission analysis which have been extensively reported in the open literature:

1. Quantitative phase analysis , it is based in the analysis of the height of the Bragg edges, through a least-squares refinement of the full TOF spectrum. The program BetMan, developed by Vogel during his Ph D Thesis, can be used for this analysis.

2. Strain and stress analysis , it is based on the precise definition of the position of individual Bragg edges. The least-squares fitting routines written by Steuwer during his Ph D Thesis have been implemented within the Data Analysis Package Open Genie, developed at ISIS, UK.

As presented in our previous report, we have implemented both data analysis programs at our laboratory, through test experiments performed on molybdenum powder. The programs were also used for the analysis of the total cross section of graphite pebbles, which have been documented in a Technical Report and will be presented on a future paper. Due to the long experimental times involved, an actual application to strain analysis experiments is waiting for the final optimization of our Bragg edge transmission beamline.

We are developing and testing a code to calculate the total cross section of textured materials, following the ideas presented in Ref. [4]. The main ingredients of the calculation are the pole figures of the material, which allow the calculation of the Orientation Distribution Function of the crystallites composing the sample. So, we have measured the transmission of aluminium and Zircaloy rolled plates along different directions; and defined their pole figures through neutron diffraction experiments performed at ISIS and LANSCE. In figure 5 we present the calculated elastic coherent total cross section for the aluminium sample presented in Figure 1. This work is in progress, but the agreement between theory and experiment is encouraging.

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III-2.5. References

[1] In-situ investigation of the reduction of NiO by a neutron transmission method , Vogel, S., Ustundag, E., Hanan, J. C., Yuan, V. W., Bourke, M. A. M., Mater. Sci. Eng. A333 (2002) 1- 9

[2] Strain imaging by Bragg edge neutron transmission, J. R. Santisteban, L. Edwards, M.E Fitzpatrick, A. Steuwer, P. J. Withers, M. R. Daymond, M. W. Johnson, N. Rhodes, E. M. Schooneveld, Nuclear Instruments and Methods in Physic Research Section A 481 (2002) 255-258

[3] A low-cost moderator for Bragg Edge Transmission analysis at small pulsed sources , J R Santisteban , A Tartaglione, L Torres, J R Granada and J J Blostein, Journal of Physics: Conference Series (in press).

[4] Characterization of textured materials by time-of-flight transmission , J. R. Santisteban, L. Edwards, V. Stelmukh, Physica B 385–386 (2006) pp. 636–638

[5] Energy-selective neutron transmission imaging at a pulsed source , W. Kockelmann, G. Frei, E.H. Lehmann, P. Vontobel, J.R. Santisteban, Nucl. Instr. Meth. A 578 (2007) pp 421- 434.

[6] Imaging and texture observation of materials by using a pulsed neutron spectroscopic transmission method , Y. Kiyanagi et al, Nuclear Instr. Methods A 600 (2009) pp 167-169

[7] NEUWAVE- 2: 2nd Workshop on Neutron Wavelength dependent imaging. Abingdon, UK, July 2009.

[8] Design of a cold neutron source for the CAB LINAC , L. Torres, Ph. D Thesis, Instituto Balseiro, Argentina, 2006.

III-2.6. ANNEX

III-2.6.1. Publications

1P1) “Experimental Neutron Data: Sigma (E) of Solid Benzene and Ice in the thermal range”, L. Torres J.R.Granada and J.J. Blostein, Nuclear Data Section, IAEA, EXFOR 31588 (2007)

2P1) “Synthetic Scattering Kernel for solid methane in phase II”J.R. Granada, Nucl.Instr.Meth. B 266 , 164 (2008)

3P1) “Neutron experiments with cryogenic methane hydrate and mesitylene moderators”, K. N¨unighoff, Ch. Pohl, S. Koulikov, F. Cantargi, H. Conrad, D. Filges, H. Gl¨uckler, F. Goldenbaum, R. Granada, G. Hansen, T. Matzerath, N. Paul, S. Petriw, H. Schaal, H. Soltner, H. Stelzer, W. Ninaus and M. Wohlmuther, Eur. Phys. J. A 38 , 115–123 (2008)

4P1) “Total cross section of solid mesitylene, toluene and a mixture of them at thermal neutron energies” , L.A. Rodriguez Palomino, F. Cantargi, J.J. Blostein, J. Dawidowski and J.R. Granada, Nuclear Instr.Meth. B 267 , 175 (2009)

5P1) “Neutron Scattering Kernel for solid Deuterium”, J.R. Granada, Eur.Phys.Lett. (in press, 2009)

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1P2) “ A Low-cost Moderator for Bragg Edge Transmission Analysis at Small Pulsed Sources” , J. Santisteban, A. Tartaglione, L. Torres, J.R. Granada, J.J. Blostein, Journal of Physics: Conference Series. ISSN 1742-6588 (submitted)

2P2) “Crystallographic Texture Profiles On Welded Zircaloy-4 Plates” , J. R. Santisteban, P. Vizcaino, L. Fernandez, R. Samper, A. D. Banchik, S. Vogel, Proceedings of the 3ra Reunión Asociación Argentina de Cristalografia, San Luis, 10-12 Octubre 2007, ISBN: 978-987- 1031-68-9 (CD ROM)

3P2) “Stress analysis by Energy Dispersive Neutron Diffraction” , J. R. Santisteban, in “Neutron and Synchrotron Radiation in Engineering Materials Science”, pp 155- 176, Editado por W. Reimers, A. R. Pyzalla, A. K. Schreyer, H. Clemens, Wiley-VCH Verlag GmbH & Co, Weinheim, Germany (2008), ISBN:3-527-31533-0

4P2) “Experimental total neutron cross section of PBMR graphite pebbles” , S. Petriw and J.R. Santisteban, CNEA/CAB Technical Report, (2008),

III-2.6.2. Contributions to Conferences

6P1) “Neutron Scattering Kernel for Solid Methane in phase II” , J.R. Granada, International Collaboration on Advanced Neutron Sources, ICANS.XVIII, Dongguan, Guangdong, China (April 2007).

7P1) “Neutron Cross Section Libraries for Aromatic Systems of Interest as Cold Neutron Moderators” , F. Cantargi, J.R. Granada, L.A. Rodríguez Palomino, S. Petriw, M.M. Sbaffoni., International Collaboration on Advanced Neutron Sources, ICANS.XVIII, Dongguan, Guangdong, China (April 2007).

8P1 ) “New Cross Section Libraries for Advanced Cold Neutron Moderators”, J.R. Granada, F. Cantargi, S. Petriw, “International Workshop on Research Reactor Utilization: 50 Years of Safe and Sustainable Operation of the IEA-R1 Research Reactor”, Sao Paulo, Brasil (3-6 Dic. 2007).

9P1) “Generation of Cold Neutron Cross Sections for Advanced Moderators” , J.R. Granada, F. Cantargi, S. Petriw. International School-Seminar “Pulsed Advanced Neutron Sources - PANS III”, Dubna, Rusia (28/01-04/02 /2008).

10P1) “Neutron Cross Section Libraries for Cryogenic Aromatic Moderator Materials” , Florencia Cantargi, J. R. Granada and María Mónica Sbaffoni, International Conference on the Physics of Reactors, PHYSOR 08, Interlaken, Switzerland (14-19 Sept 2009).

11P1) “ A Low-cost Moderator for Bragg Edge Transmission Analysis at Small Pulsedth Sources” , J. Santisteban, A. Tartaglione, L. Torres, J.R. Granada, J.J. Blostein, 9 International Cenference on Neutron Scattering , Knoxville, Tennessee, USA, 3 - 7 May 2009.

12P1) “Development of Cold Neutron Scattering Kernels for Advanced Moderators” J.R. Granada, International Conference on “Neutron and X-Ray Scattering 2009”, Kuala Lumpur, Malaysia, 29 Jun - 1 July 2009.

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III-2.6.3. Collaboration within this CRP

13P1) “Thermal Neutron Cross Section Data for Water Ice and Mesitylene at 100K”, S. Petriw, F. Cantargi, and J.R. Granada, Informe Tecnico CNEA-CAB 420/027/07, (Prepared as Scientific Document accompanying the cross section libraries sent to Mr. Basu at BARC)

III-2.6.4. Doctoral Thesis

“Generacion de datos nucleares para moderadores criogénicos y de altas temperaturas” , S. Petriw, PhD Thesis, Instituto Balseiro (2007), Supervisor: J.R. Granada

“Propiedades neutrónicas de hidrocarburos aromáticos como moderadores criogénicos” , F. Cantargi, PhD Thesis, Instituto Balseiro (2007), Supervisor: J.R. Granada

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