UNITED NATIONS Geneva 1958 A/CONF.15/1 English, Vol
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小型飛翔体/海外 [Format 2] Technical Catalog Category
小型飛翔体/海外 [Format 2] Technical Catalog Category Airborne contamination sensor Title Depth Evaluation of Entrained Products (DEEP) Proposed by Create Technologies Ltd & Costain Group PLC 1.DEEP is a sensor analysis software for analysing contamination. DEEP can distinguish between surface contamination and internal / absorbed contamination. The software measures contamination depth by analysing distortions in the gamma spectrum. The method can be applied to data gathered using any spectrometer. Because DEEP provides a means of discriminating surface contamination from other radiation sources, DEEP can be used to provide an estimate of surface contamination without physical sampling. DEEP is a real-time method which enables the user to generate a large number of rapid contamination assessments- this data is complementary to physical samples, providing a sound basis for extrapolation from point samples. It also helps identify anomalies enabling targeted sampling startegies. DEEP is compatible with small airborne spectrometer/ processor combinations, such as that proposed by the ARM-U project – please refer to the ARM-U proposal for more details of the air vehicle. Figure 1: DEEP system core components are small, light, low power and can be integrated via USB, serial or Ethernet interfaces. 小型飛翔体/海外 Figure 2: DEEP prototype software 2.Past experience (plants in Japan, overseas plant, applications in other industries, etc) Create technologies is a specialist R&D firm with a focus on imaging and sensing in the nuclear industry. Createc has developed and delivered several novel nuclear technologies, including the N-Visage gamma camera system. Costainis a leading UK construction and civil engineering firm with almost 150 years of history. -
The Effect of Gamma Radiation on Fibre Bragg Grating Sensors When Used As Radiation Dosimeters
Edith Cowan University Research Online Theses : Honours Theses 2013 The effect of gamma radiation on fibre Bragg grating sensors when used as radiation dosimeters Des Baccini Edith Cowan University Follow this and additional works at: https://ro.ecu.edu.au/theses_hons Part of the Nuclear Engineering Commons, and the Semiconductor and Optical Materials Commons Recommended Citation Baccini, D. (2013). The effect of gamma radiation on fibre Bragg grating sensors when used as radiation dosimeters. https://ro.ecu.edu.au/theses_hons/79 This Thesis is posted at Research Online. https://ro.ecu.edu.au/theses_hons/79 Edith Cowan University Research Online Theses : Honours Theses 2013 The effect of gamma radiation on fibre Bragg grating sensors when used as radiation dosimeters Des Baccini Edith Cowan University Recommended Citation Baccini, D. (2013). The effect of gamma radiation on fibre Bragg grating sensors when used as radiation dosimeters. Retrieved from http://ro.ecu.edu.au/theses_hons/79 This Thesis is posted at Research Online. http://ro.ecu.edu.au/theses_hons/79 Edith Cowan University Copyright Warning You may print or download ONE copy of this document for the purpose of your own research or study. The University does not authorize you to copy, communicate or otherwise make available electronically to any other person any copyright material contained on this site. You are reminded of the following: Copyright owners are entitled to take legal action against persons who infringe their copyright. A reproduction of material that is protected by copyright may be a copyright infringement. A court may impose penalties and award damages in relation to offences and infringements relating to copyright material. -
Space Radiation Effects on Electronics: Simple Concepts and New Challenges
Space Radiation Effects on Electronics: Simple Concepts and New Challenges Kenneth A. LaBel [email protected] Co-Manager, NASA Electronic Parts and Packaging (NEPP) Program Group Leader, Radiation Effects and Analysis Group (REAG), NASA/GSFC Project Technologist, Living With a Star (LWS) Space Environment Testbeds (SET) Outline • The Space Radiation Environment • The Effects on Electronics • The Environment in Action • NASA Approaches to Commercial Electronics – The Mission Mix – Flight Projects – Proactive Research • Final Thoughts Atomic Interactions – Direct Ionization Interaction with Nucleus – Indirect Ionization http://www.stsci.edu/hst/nicmos/performance/anomalies/bigcr.html – Nucleus is Displaced 2 Space Radiation Effects on Electronics presented by Kenneth A. LaBel at 2004 MRS Fall Meeting, Boston, MA – Nov 29, 2004 The Space Radiation Environment STARFISH detonation – Nuclear attacks are not considered in this presentation Space Environments and Related Effects Micro- Plasma Particle Neutral Ultraviolet meteoroids & radiation gas particles & X-ray orbital debris Ionizing & Single Surface Charging Drag Impacts Non-Ionizing Event Erosion Dose Effects •Biasing of •Degradation •Data •Torques •Degradation •Structural instrument of micro- corruption •Orbital of thermal, damage • electrical, readings electronics •Noise on decay •Decompression optical •Degradation Images •Pulsing properties of optical •System •Power •Degradation components shutdowns drains of structural •Degradation •Physical •Circuit integrity of solar cells damage -
Fuel Geometry Options for a Moderated Low-Enriched Uranium Kilowatt-Class Space Nuclear Reactor T ⁎ Leonardo De Holanda Mencarinia,B,Jeffrey C
Nuclear Engineering and Design 340 (2018) 122–132 Contents lists available at ScienceDirect Nuclear Engineering and Design journal homepage: www.elsevier.com/locate/nucengdes Fuel geometry options for a moderated low-enriched uranium kilowatt-class space nuclear reactor T ⁎ Leonardo de Holanda Mencarinia,b,Jeffrey C. Kinga, a Nuclear Science and Engineering Program, Colorado School of Mines (CSM), 1500 Illinois St, Hill Hall, 80401 Golden, CO, USA b Subdivisão de Dados Nucleares - Instituto de Estudos Avançados (IEAv), Trevo Coronel Aviador José Alberto Albano do Amarante, n 1, 12228-001 São José dos Campos, SP, Brazil ABSTRACT A LEU-fueled space reactor would avoid the security concerns inherent with Highly Enriched Uranium (HEU) fuel and could be attractive to signatory countries of the Non-Proliferation Treaty (NPT) or commercial interests. The HEU-fueled Kilowatt Reactor Using Stirling Technology (KRUSTY) serves as a basis for a similar reactor fueled with LEU fuel. Based on MCNP6™ neutronics performance estimates, the size of a 5 kWe reactor fueled with 19.75 wt% enriched uranium-10 wt% molybdenum alloy fuel is adjusted to match the excess reactivity of KRUSTY. Then, zirconium hydride moderator is added to the core in four different configurations (a homogeneous fuel/moderator mixture and spherical, disc, and helical fuel geometries) to reduce the mass of uranium required to produce the same excess reactivity, decreasing the size of the reactor. The lowest mass reactor with a given moderator represents a balance between the reflector thickness and core diameter needed to maintain the multiplication factor equal to 1.035, with a H/D ratio of 1.81. -
Delayed Hydride Cracking in Zirconium Alloys in Pressure Tube Nuclear Reactors
IAEA-TECDOC-1410 Delayed hydride cracking in zirconium alloys in pressure tube nuclear reactors Final report of a coordinated research project 1998–2002 October 2004 IAEA-TECDOC-1410 Delayed hydride cracking in zirconium alloys in pressure tube nuclear reactors Final report of a coordinated research project 1998–2002 October 2004 The originating Section of this publication in the IAEA was: Nuclear Power Technology Development Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria DELAYED HYDRIDE CRACKING IN ZIRCONIUM ALLOYS IN PRESSURE TUBE NUCLEAR REACTORS IAEA, VIENNA, 2004 IAEA-TECDOC-1410 ISBN 92–0–110504–5 ISSN 1011–4289 © IAEA, 2004 Printed by the IAEA in Austria October 2004 FOREWORD This report documents the work performed in the Coordinated Research Project (CRP) on Hydrogen and Hydride Degradation of the Mechanical and Physical Properties of Zirconium Alloys. The Project consisted of hydriding samples of Zr-2.5 Nb pressure tube materials used in CANDU-type and RBMK reactors, the measurement of delayed hydride cracking (DHC) rates under specified conditions, and analysis of hydrogen concentrations. The project was overseen by a supervisory group of experts in the field who provided advice and assistance to the participants as required. All of the research work undertaken as part of the CRP is described in this report, which includes a review of the state of the art in understanding crack propagation by DHC and details of the experimental procedures that produced the most consistent set of DHC rates reported in an international round-robin exercise to this date. All of the participants and many of their co-workers in the laboratories involved in the CRP contributed results and material used in the drafting of this report, which contains compilations of all of the results, their analysis, discussions of their interpretation and conclusions and recommendations for further work. -
NETS 2020 Template
بÀƵƧǘȁǞƧƊǶ §ȲȌǐȲƊǿ ƊƧDzɈȌɈǘƵwȌȌȁƊȁƮȌȁ ɈȌwƊȲȺɈǘȲȌɐǐǘƊƮɨƊȁƧǞȁǐ خȁɐƧǶƵƊȲɈƵƧǘȁȌǶȌǐǞƵȺƊȁƮ ǞȁȁȌɨƊɈǞȌȁ ǞȺ ȺȯȌȁȺȌȲƵƮ Ʀɯ ɈǘƵ ƊDz ªǞƮǐƵ yƊɈǞȌȁƊǶ ׁׂ׀ׂ y0À² ÀǘǞȺ ƧȌȁǏƵȲƵȁƧƵ خׁׂ׀ׂ ةɈǘ׀׃ƊȁƮ ɩǞǶǶƦƵ ǘƵǶƮ ǏȲȌǿȯȲǞǶ ׂ׆ɈǘٌةmƊƦȌȲƊɈȌȲɯ ɩǞǶǶ ƦƵ ǘƵǶƮ ɨǞȲɈɐƊǶǶɯ ȺȌ ɈǘƊɈ ɈǘƵ ƵȁɈǞȲƵ y0À² خƧȌǿǿɐȁǞɈɯǿƊɯȯƊȲɈǞƧǞȯƊɈƵǞȁɈǘǞȺƵɮƧǞɈǞȁǐǿƵƵɈǞȁǐ ǐȌɨخȌȲȁǶخخׁׂ׀ȁƵɈȺׂششبǘɈɈȯȺ Nuclear and Emerging Technologies for Space Sponsored by Oak Ridge National Laboratory, April 26th-30th, 2021. Available online at https://nets2021.ornl.gov Table of Contents Table of Contents .................................................................................................................................................... 1 Thanks to the NETS2021 Sponsors! ...................................................................................................................... 2 Nuclear and Emerging Technologies for Space 2021 – Schedule at a Glance ................................................. 3 Nuclear and Emerging Technologies for Space 2021 – Technical Sessions and Panels By Track ............... 6 Nuclear and Emerging Technologies for Space 2021 – Lightning Talk Final Program ................................... 8 Nuclear and Emerging Technologies for Space 2021 – Track 1 Final Program ............................................. 11 Nuclear and Emerging Technologies for Space 2021 – Track 2 Final Program ............................................. 14 Nuclear and Emerging Technologies for Space 2021 – Track 3 Final Program ............................................. 18 -
Advanced Reactors with Innovative Fuels
Nuclear Science Advanced Reactors with Innovative Fuels Workshop Proceedings Villigen, Switzerland 21-23 October 1998 NUCLEAR•ENERGY•AGENCY OECD, 1999. Software: 1987-1996, Acrobat is a trademark of ADOBE. All rights reserved. OECD grants you the right to use one copy of this Program for your personal use only. Unauthorised reproduction, lending, hiring, transmission or distribution of any data or software is prohibited. You must treat the Program and associated materials and any elements thereof like any other copyrighted material. All requests should be made to: Head of Publications Service, OECD Publications Service, 2, rue AndrÂe-Pascal, 75775 Paris Cedex 16, France. OECD PROCEEDINGS Proceedings of the Workshop on Advanced Reactors with Innovative Fuels hosted by Villigen, Switzerland 21-23 October 1998 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT Pursuant to Article 1 of the Convention signed in Paris on 14th December 1960, and which came into force on 30th September 1961, the Organisation for Economic Co-operation and Development (OECD) shall promote policies designed: − to achieve the highest sustainable economic growth and employment and a rising standard of living in Member countries, while maintaining financial stability, and thus to contribute to the development of the world economy; − to contribute to sound economic expansion in Member as well as non-member countries in the process of economic development; and − to contribute to the expansion of world trade on a multilateral, non-discriminatory basis in accordance with international obligations. The original Member countries of the OECD are Austria, Belgium, Canada, Denmark, France, Germany, Greece, Iceland, Ireland, Italy, Luxembourg, the Netherlands, Norway, Portugal, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States. -
THE KINETICS OP the REDUCTION of URANIUM TETRAFLUORIDE by MAGNESIUM in the Jose T. I. Domingues London, May, 1964
THE KINETICS OP THE REDUCTION OF URANIUM TETRAFLUORIDE BY MAGNESIUM A thesis presented for the degree of Doctor of Philosophy in the University of London by Jose T. I. Domingues London, May, 1964 ABSTRACT The kinetics of the reduction of sintered UF4 pellets by Mg vapour was investigated at 620° and 69000, using a transportation technique and highly purified argon as the carrier gas. The products of the reaction were identified by microscopic observation of cross sections and by X-ray powder diffraction, electron probe and chemical analyses. Two coherent product layers (UF and MgF2) are formed on the UF the uranium metal 3 4' being interspersed in the outer layer (MgF2) as fine globules or thin lamellae. Marker experiments showed 2+ that the MgF2 layer grows by inward migration of Mg ions and the UF layer grows inwards probably by outward 3 migration of fluorine ions. The rate of both reactions follows a parabolic rate law, after an initial period for which a different law applies, probably a direct logarithmic relationship. A discussion is given of the possible mechanisms in the two cases. From reduction experiments with UF3 pellets it was demonstrated that migration through the MgF2 layer is the rate determining step of the overall reaction. The parabolic rate constants for the overall reaction are 1.8 x 10-11 and 4.75 x 10-10 g2cm-4min-1 at 620° and 690°C respectively. The parabolic rate constants for the partial reaction yielding UF3 are 6.7 x 10-13 and 1.1 x 10-1° g2cni4min-1.- The industrial process of bomb production of uranium was reviewed and discussed, and suggestions are made for the interpretation of the mechanism of ignition of the reaction by a simple theory of self heating. -
Investigation of Evaporation Characteristics of Polonium and Its Lighter Homologues Selenium and Tellurium from Liquid Pb-Bi-Eutecticum
EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH CERN-PH-EP/2004-061 18 November 2004 Investigation of evaporation characteristics of polonium and its lighter homologues selenium and tellurium from liquid Pb-Bi-eutecticum J. Neuhausen*1, U. Köster2 and B. Eichler1 1Laboratory for Radio- and Environmental Chemistry; Paul Scherrer Institute, CH-5232 Villigen PSI, Switzerland 2CERN, ISOLDE, CH-1211 Genève 23, Switzerland Abstract The evaporation behaviour of polonium and its lighter homologues selenium and tellurium dissolved in liquid Pb-Bi-eutecticum (LBE) has been studied at various temperatures in the range from 482 K up to 1330 K under Ar/H2 and Ar/H2O-atmospheres using γ-ray spectroscopy. Polonium release in the temperature range of interest for technical applications is slow. Within short term (1h) experiments measurable amounts of polonium are evaporated only at temperatures above 973 K. Long term experiments reveal that a slow evaporation of polonium occurs at temperatures around 873 K resulting in a fractional polonium loss of the melt around 1% per day. Evaporation rates of selenium and tellurium are smaller than those of polonium. The presence of H2O does not enhance the evaporation within the error limits of our experiments. The thermodynamics and possible reaction pathways involved in polonium release from LBE are discussed. (Submitted to Radiochimica Acta) * Author for correspondence (E-mail: [email protected]). 2 1. Introduction Liquid Lead-Bismuth eutecticum (LBE) is proposed to be used as target material in spallation neutron sources [1] as well as in Accelerator Driven Systems (ADS) for the transmutation of long-lived nuclear waste [2]. In these systems polonium is formed as a product of (p,xn) and (n,γ)-reactions according to the following processes: 209Bi ⎯⎯(p,xn)⎯→208,209Po (1) γ β − 209Bi ⎯⎯(n,⎯)→210Bi ⎯⎯→⎯ 210Po (2) Within 1 year of operation employing a proton beam current of 1 mA around 2 g of polonium are produced in this manner [3]. -
A44 24 -2/ 124-Ea L-E
March 6, 1951 A. S. NEWTON ETAL 2,544,277 PREPARATION OF URANIUM NITRIDE Filed June 12, 1945 %22%2 SC22222222222222222SSaccaccounccc. 5 V. N 2&383i;3. &4 SSSSSSSSSSSSS Awar areakawazaarawawaramaranaergamawaramarasaaaaaaaaara SSSSSS sys SSSSSSSS & S is SSS S S. S. S. wavvavusavus Avavas Awar. us 2/22ZZzesses. s -aas/2za/2Zzao 2.1222/a2zz Yrs: %24427 6222227? 72/2Zasto Zz A44 24 -2/ 124-ea-222//zesz. l-e- Patented Mar. 6, 1951 2,544,277 UNITED STATES PATENT OFFICE 2,544,277 PREPARATION OF URANIUMNITRIDE Amos S. Newton and Oliver Johnson, Annes, Iowa, assignors to the United States of Arinerica, as represented by the United States Atomic En ergy Commission Application June 12, 1945, Seria No. 599,067 2 Claims. (CI. 23-14.5) 2 The invention relates to the preparation of a tion 8 and casing 9. Inlet tubes 9 and uranium nitride. are attached to a Source of ammonia, hydrogen, It is an object of the invention to provide a or other gaseous reactant to be used in the proc uranium nitride by the reaction of uranium either ess. Exhaust tube 8 leads to any suitable means in compound form or as a metal with ammonia. for disposing of waste products exhausted dur or nitrogen. ing the process. The apparatus is formed of a It is a more specific object of the invention material which is resistant to the high tempera to provide a process for obtaining a pure product tures and corrosion resulting from the process. in which the uranium is prepared in reactable Heat resistant glass is suitable for this purpose. -
Alfred O. C. Nier
CHEMICAL HERITAGE FOUNDATION ALFRED O. C. NIER Transcript of Interviews Conducted by Michael A. Grayson and Thomas Krick at University of Minnesota Minneapolis, Minnesota on 7, 8, 9, and 10 April 1989 (With Subsequent Corrections and Additions) ACKNOWLEDGMENT This oral history is one in a series initiated by the Chemical Heritage Foundation on behalf of the American Society for Mass Spectrometry. The series documents the personal perspectives of individuals related to the advancement of mass spectrometric instrumentation, and records the human dimensions of the growth of mass spectrometry in academic, industrial, and governmental laboratories during the twentieth century. This project is made possible through the generous support of the American Society for Mass Spectrometry Upon Alfred O.C. Nier’s death in 1994, this oral history was designated Free Access. Please note: Users citing this interview for purposes of publication are obliged under the terms of the Chemical Heritage Foundation Oral History Program to credit CHF using the format below: Alfred O.C. Nier, interview by Michael A. Grayson and Thomas Krick at the University of Minnesota, Minneapolis, Minnesota, 7-10 April 1989 (Philadelphia: Chemical Heritage Foundation, Oral History Transcript # 0112). Chemical Heritage Foundation Oral History Program 315 Chestnut Street Philadelphia, Pennsylvania 19106 The Chemical Heritage Foundation (CHF) serves the community of the chemical and molecular sciences, and the wider public, by treasuring the past, educating the present, and inspiring the future. CHF maintains a world-class collection of materials that document the history and heritage of the chemical and molecular sciences, technologies, and industries; encourages research in CHF collections; and carries out a program of outreach and interpretation in order to advance an understanding of the role of the chemical and molecular sciences, technologies, and industries in shaping society. -
Radioactive Waste Management Programmes in OECD/NEA Member Countries – Overview
Cov-Eng-Pochette 2005 21/09/05 15:04 Page 1 Australia Radioactive Waste Belgium Canada Management Programmes Czech Republic Finland in OECD/NEA Member France Countries Germany Hungary Italy Japan Korea Mexico Netherlands Norway Slovak Republic Spain Sweden Switzerland United Kingdom United States NUCLEAR•ENERGY•AGENCY 1-OVERVIEW.qxp 16/11/05 17:18 Page 1 Radioactive waste management programmes in OECD/NEA member countries – Overview International co-operation at the OECD/NEA concerning the management of radioactive waste and materials The role of the NEA Radioactive Waste Management Committee (RWMC) Radioactive waste and materials exist in countries Strategies with and without nuclar power programmes and need In particular, the RWMC facilitates the elaboration to be managed in a manner that is responsible to pres- of strategies for waste management and decommis- ent and future generations. Significant progress has sioning, including regulatory approaches, at the been achieved and considerable experience is avail- national and international levels by: able in NEA member countries on waste and mate- ● reviewing strategies adopted by member countries rials processing, conditioning, storage, transport and with a view to identify and analyse emerging tech- disposal. An important experience and knowledge nical, policy and regulatory issues and to forge base has also been developed as regards decommis- consensus views; sioning and dismantling nuclear installations. Special ● reviewing regulatory bases, requirements and efforts are being expended in the area of long-term criteria, and licensing processes, in addition to management of radioactive waste in order to continue proposing regulatory approaches; to integrate technical advances and societal demands ● in decision making as well as to understand and developing methodologies for evaluating long-term develop consensus views on regulatory and policy safety; ● issues.