Neutron Scattering at HIFAR—Glimpses of the Past
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The Jules Horowitz Reactor Project, a Driver for Revival of the Research Reactor Community
THE JULES HOROWITZ REACTOR PROJECT, A DRIVER FOR REVIVAL OF THE RESEARCH REACTOR COMMUNITY P. PERE, C. CAVAILLER, C. PASCAL AREVA TA CEA Cadarache - Etablissement d'AREVA TA - Chantier RJH - MOE - BV2 - BP n° 9 – 13115 Saint Paul lez Durance - France CS 50497 - 1100, rue JR Gauthier de la Lauzière, 13593 Aix en Provence cedex 3 – France ABSTRACT The first concrete of the nuclear island for the Jules Horowitz Reactor (JHR) was poured at the end of July 2009 and construction is ongoing. The JHR is the largest new platform for irradiation experiments supporting Generation II and III reactors, Generation IV technologies, and radioisotope production. This facility, composed of a unique grouping of workshops, hot cells and hot laboratories together with a first -rate MTR research reactor, will ensure that the process, from preparations for irradiation experiments through post-irradiation non-destructive examination, is completed expediently, efficiently and, of course, safely. In addition to the performance requirements to be met in terms of neutron fluxes on the samples (5x1014 n.cm-2/sec-1 E> 1 MeV in core and 3,6x1014 n.cm-2/sec-1 E<0.625 eV in the reflector) and the JHR’s considerable irradiation capabilities (more than 20 experiments and one-tenth of irradiation area for simultaneous radioisotope production), the JHR is the first MTR to be built since the end of the 1960s, making this an especially challenging project. The presentation will provide an overview of the reactor, hot cells and laboratories and an outline of the key milestones in the project schedule, including initial criticality in early 2014 and radioisotope production in 2015. -
Decommissioning of Nuclear Facilities in Switzerland – Lessons Learned
WIR SCHAFFEN WISSEN – HEUTE FÜR MORGEN Fritz Leibundgut :: Decommissioning Officer :: Paul Scherrer Institut Decommissioning of Nuclear Facilities in Switzerland – Lessons learned HRP/IAEA/NEA Decommissioning workshop – February 7, 2017 Overview Basel Germany Aarau/Bern Zürich material sciences nanotechnology radio chemistry hotlab radio pharmacy biology PSI east solar concentrator energy research SwissFEL particle physics proton accelerator neutron source muon source proton therapy PSI west synchrotron light source Page 2 Nuclear installations on the PSI area • (ZWILAG) • AERA with VVA* • Hotlabor • DIORIT* • SAPHIR* • PROTEUS* *Post-operation phase/ Decomm./Dismantling Page 3 SAPHIR: 1957-1993 First reactor in Switzerland; used for isotope production, reactor training, neutron source for various experiments 1955 USA exposed a reactor at the “Atoms for Peace” conference in Geneva 1956 Laying of the cornerstone in Würenlingen 1957 First criticality 1960 Approval by Swiss government 1985 Approval for 10 MW 1993 Final shutdown 2000 Decommissioning ordinance 2008 Dismantling of the pool completed 2015 Cleanout of the KBL (“Kernbrennstofflager”) Page 4 SAPHIR: Status 2016 ENSI-Inspection at 7. of April, 2016 Page 5 DIORIT: 1960-1977 Proprietary Swiss development. Goal was the construction of industrial applicable reactors for material testings and experiments. 1960 Operation with natural uranium and D2O as coolant and moderator. 1966 Uprating from 20 MW to 30 MW. 1972 (after modification): Operation with LEU. 1977 Final shutdown. 1982 Partial dismantling; continued 1988-1993. 1994 Approval of dismantling the reactor. 2005 Asbestos was found interruption until 2009. 2013 Dismantling of biological shielding 2016 Cutting of the „Arbeitsboden“ (22 t activated Fe) 2019 (?) 2. Decommissioning ordinance for greenfield Page 6 DIORIT PSI, 23.10.2016 Page 7 Biol. -
German Research Reactor
German Research Reactor Back-end Provisions RERTR 2002 San Carlos de Bariloche, Argentina Nov-3/8 Authors: Siegfried Koester/German Federal Ministry of Economics and Technology Gerhard Gruber/RWE NUKEM GmbH On behalf of the German Working Group Back-end for Research Reactors Fuel Cycle History of Half a Century US 'Atoms for Peace Program', President Eisenhower 1953 HEU for peaceful research and development (R&D) First RR built in Germany in the late 1950s US supplied fuel on a lease basis until 1974 Until 1987 fuel sale with option to return spent HEU + LEU fuel 1987-Dec-31: DOE's policy for receipt of FRR SNF expires without prior notice German RR Back-end History 1960s: US Reprocessing, no return of waste 1960/70s: UK Reprocessing, no return of waste 1970s: Belgium + France Reprocessing, no return of waste 1980s: US Reprocessing, no return of waste 1990s: UK Reprocessing, mandatory waste return Current German Back-end Solution 1996 - 2006: Return SNF to US under 'FRR SNF Return Policy' (US-origin) Non-Proliferation: Return of all HEU to the US 2 Promote RR conversion to LEU 10 yrs to provide for national Back-end solutions Establish int. Back-end solutions (e.g. IAEA promotion) German Spent RR Fuel Output Current Reactors (operation time): 'BER-II' (2015), 'FRG-1' (> 2010), 'FRJ-2' (2005?), 'TRIGA-MZ' (>2010), 8 'SUR’ Future Reactors: 'FRM-II' (2003-2033), 'NN' (possibly needed > 2010) Fuels: U-Al, U-Si, U-ZrH, U-PE, U-Mo in future US- and RUS-origin RUS-origin: 'FRM-II' + 'RFR' (shut down) with 1,000 FE leftover -
Material Test Reactors and Other Irradiation Facilities
M A T E R I A L T E S T R EACTORS AND OTHER I RRADIATION F ACILITIES Material Test Reactors and other Irradiation Facilities Authors Tahir Mahmood Pleasanton, CA, USA Malcolm Griffiths Deep River, ON, Canada Clément Lemaignan Voreppe, France Ron Adamson Fremont, CA, USA © November 2018 Advanced Nuclear Technology International Spinnerivägen 1, Mellersta Fabriken plan 4, 448 50 Tollered, Sweden [email protected] www.antinternational.com M A T E R I A L T E S T R EACTORS AND OTHER I RRADIATION F ACILITIES Disclaimer The information presented in this report has been compiled and analysed by Advanced Nuclear Technology International Europe AB (ANT International®) and its subcontractors. ANT International has exercised due diligence in this work, but does not warrant the accuracy or completeness of the information. ANT International does not assume any responsibility for any consequences as a result of the use of the information for any party, except a warranty for reasonable technical skill, which is limited to the amount paid for this report. Quality-checked and authorized by: Mr Peter Rudling, President of ANT International Copyright © Advanced Nuclear Technology International Europe AB, ANT International, 2018. I(V) M A T E R I A L T E S T R EACTORS AND OTHER I RRADIATION F ACILITIES Contents Introduction IV 1 Material Test Reactors (MTRs) (Tahir Mahmood) 1-1 1.1 Introduction 1-1 1.1.1 Research reactors 1-1 1.1.2 Types of research reactors 1-2 1.1.3 Material test reactors 1-3 1.2 Material test reactors – IAEA database 1-5 1.3 Characteristics -
Institute for Nuclear Research and Nuclear Energy Bulgarian Academy of Sciences
Institute for Nuclear Research and Nuclear Energy Bulgarian Academy of Sciences 20102010 Present State Future Prospects Short History The Physical Institute of the Bulgarian Academy of Sciences (BAS) was established on 1 July 1946 by academician Georgi Nadjakov who became its first director. JINR, Dubna, was established on 26 March 1956 Acad. G. Nadjakov was signing the Protocol together with 10 representatives of other countries. In the autumn of 1955 the Bulgarian government took a decision to build a research nuclear reactor. In 1962 the Physical Institute of BAS was renamed as the Physical Institute with a Nuclear Experimental Facility. In 1972 it was splited into Institute for Nuclear Research and Nuclear Energy (INRNE) and Institute of Solid State Physics. Mission The Institute for Nuclear Research and Nuclear Energy (INRNE) of the Bulgarian Academy of Sciences is the biggest leading complex centre in Bulgaria for scientific research and applications of the nuclear science and technologies and studies of their interactions with the environment. Vision INRNE guarantees a high quality performance of research and innovation activities, addressed to support important national programs, keeping abreast with the modern scientific achievements. With its long standing experience and active collaboration with leading European and International institutions, INRNE contributes to the progress of the physical science. Since 2003/2004 INRNE BAS is certificated ISO 9001:2000 №3312/0 according to ISO 14001:2004 №357/0 Staff and Budget 14 74 126 -
Treatment of Spent Fuels from Research Reactors and Reactor Development Programs in Germany
TREATMENT OF SPENT FUELS FROM RESEARCH REACTORS AND REACTOR DEVELOPMENT PROGRAMS IN GERMANY K.D. CLOSS XA9949808 Forschungszentrum Karlsruhe, Karlsruhe, Germany Abstract Quite a great number of different types of spent fuel from research reactors and development programs exists in Germany. The general policy is to send back to the USA as long as possible fuel from MTRs and TRIG As of USA origin. An option is reprocessing in Great Britain or France. This option is pursued as long as reprocessing and reuse of the recovered material is economically justifiable. For those fuels which cannot be returned to the USA or which will not be reprocessed, a domestic back-up solution of spent fuel management has been developed in Germany, compatible with the management of spent fuel from power reactors. It consists in dry storage in special casks and, later on, direct disposal. Preliminary results from experimental R&D inves- tigations with research reactor fuel and experience from LWR fuel lead to the conclusion that the direct dis- posal option even for research reactor fuel or exotic fuel does not impose major technical difficulties for the German waste management and disposal concept. 1. RESEARCH AND EXPERIMENTAL REACTORS IN GERMANY At the end of 1997, six research reactors with a power > 100 kW were operating in Germany. These comprise two TRIGA-type reactors, three swimming-pool reactors and one DIDO-type reactor. Moreover, one new research reactor is under construction, the operational start-up of which is expected in 2001. More details of these reactors are given in Table I. In addition to these reactors, there are eight research reactors permanently shut down, some of which have already been dismantled. -
Neutrons for the Nation Discovery and Applications While Minimizing the Risk of Nuclear Proliferation
Neutrons for the Nation Discovery and Applications while Minimizing the Risk of Nuclear Proliferation A Report by the APS Panel on Public Affairs July 2018 ABOUT APS & POPA AUTHORSHIP Founded in 1899 to advance and diffuse the knowledge of The American Physical Society has sole responsibility for physics, the American Physical Society (APS) is now the nation’s the contents of this report, and the questions, findings, and leading organization of physicists with approximately 55,000 recommendations within. members in academia, national laboratories and industry. APS has long played an active role in the federal government; its members serve in Congress and have held positions such as Science Advisor to the President of the United States, Director ACKNOWLEDGEMENTS of the CIA, Director of the National Science Foundation and We thank Frank Bates, Bill Buyers, David Dean, Alex Glaser, Secretary of Energy. Geoff Greene, Jenny Heimberg, Mark Johnson, John Katsaras, Julia Kornfield, Patrick Lemoine, Dan Neumann, Sean O’Kelly, This report was overseen by the APS Panel on Public Affairs Ray Orbach, Winfried Petry, Roger Pynn, Kate Ross, and (POPA). POPA routinely produces reports on timely topics J. Michael Rowe for their contributions to this report. being debated in government so as to inform the debate with the perspectives of physicists working in the relevant issue areas. PUBLICATION DATE: JULY 2018 REPORT COMMITTEE American Physical Society James Wells, Co-Chair, University of Michigan Physics This report is available under the terms of a Creative Commons Department Attribution 4.0 International License. Sharing and adapting the material for any purpose, even commercial, does not require Julia Phillips, Co-Chair, Sandia National Laboratory prior written permission. -
Annual Report 1991: Operation of the High Flux
f ë[yKj:/(/i ¿f. ANNUAL REPORT 1¡99 1 OPERATION OF THE HIGH FLUXREACTOR JOINT RESEARCH CENTRE COMMISSION OF THE EUROPEAN COMMUNITIES ■ ":: ''K'iáOí'.1' ANNUAL REPORT 1991 OPERATION OF THE HIGH FLUX REACTOR J. AHLF, A. GEVERS, editors FA8L EötOf». W& ex Commission of the European Communities JOINT RESEARCH CENTRE Institute for Advanced Materials Petten Site NUCLEAR SCIENCE AND TECHNOLOGY DIRECTORATE-GENERAL SCIENCE, RESEARCH AND DEVELOPMENT 1992/EUR 14416 EN Published by the Commission of the European Communities Directorate-General Telecommunications, Information Industries and Innovation L-2920 Luxembourg Catalogue number: CD-NA 14416-EN-C © ECSC-EEC-EAEC, Brussels - Luxembourg, 1992 Legal Notice Neither the Commission of the European Communities nor any person acting on behalf of the Commission is responsible for the use which might be made of the following information TABLE OF CONTENTS 1. INTRODUCTION 5 ANNUAL REPORT 1991 2. HFR OPERATION, MAINTENANCE, DEVELOPMENT AND SUPPORT 7 2.1. Operation 7 2.2. Fuel Cycle 10 2.3. Safety and Quality Management 11 2.4. Technical Maintenance 11 2.5. Technical and Experimental Support 16 2.6. Upgrading and Modification Projects 16 2.7. Nuclear Support 18 3. HFR UTILIZATION 20 3.1. Light Water Reactor (LWR). Fuel and Structural Material Irradiations 21 3.2. Fast Breeder Reactor (FBR). Fuel and Structural Material Irradiations 27 3.3. High Temperature Reactor (HTR). Fuel and Graphite Irradiations 32 3.4. Fusion Reactor Material Irradiations 39 3.5. Radionuclide Production 58 3.6. Activation Analysis 59 3.7. Solid State Physics and Materials Science 60 3.8. Boron Neutron Capture Therapy (BNCT) 61 3.9. -
Assessment of Missions and Requirements for a New U.S. Test Reactor
Nuclear Energy Advisory Committee Assessment of Missions and Requirements for a New U.S. Test Reactor Draft Report December 2016 i Table of Contents ii Acronyms ANL Argonne National Laboratory ANSTO Australian Nuclear Science and Technology Organisation ATR Advanced Test Reactor BARC Bhabha Atomic Research Centre CAEA China Atomic Energy Authority CEA Commissariat à l’Energie Atomique et aux Energies Alternatives CNEA National Atomic Energy Commission DOD Department of Defense DOE Department of Energy DOE-NE Department of Energy -Office of Nuclear Energy dpa displacements per atom ESAAB Energy Systems Acquisition Advisory Board EBR-II Experimental Breeder Reactor-II GCR Gas-Cooled Reactor GIF Generation IV International Forum FFTF Fast Flux Test Facility FHR Fluoride Salt-Cooled High Temperature Reactor HFIR High Flux Isotope Reactor HTGR High Temperature Gas-cooled reactors HTR-PM High Temperature gas-cooled Reactor Pebble-bed Module IFE Institute for Energy Technology IGCAR Indira Gandhi Centre for Atomic Research IKET Institute for Nuclear and Energy Technologies ININ Instituto Nacional de Investigaciones Nucleare INL Idaho National Laboratory JAEA Japan Atomic Energy Agency (JAEA) KAERI Korea Atomic Energy Research Institute KIT Karlsruhe Institute of Technology LANL Los Alamos National Laboratory LWR Light Water Reactor iii LFR Lead Fast Reactor MITR Massachusetts Institute of Technology Research Reactor MOST Ministry of Science and Technology MSR Molten Salt Reactor MTR Material Test Reactor NAS National Academy of Science NBSR National Bureau of Standards Reactor NEAC Nuclear Energy Advisory Committee NEI Nuclear Energy Institute NRT SC Nuclear Reactor Technology Subcommittee NASA National Aeronautics and Space Administration NNSA National Nuclear Security Administration NRC U.S. -
A National Strategy for Materials Research with Neutron Beams
DRAFT FOR CONSULTATION A National Strategy for Materials Research with Neutron Beams A discussion paper for the Roundtable Meeting, “Canadian Neutron Initiative: Towards a National Neutron Strategy” To be held as a virtual event, December 15–16, 2020 Updated Dec 10, 2020 1 DRAFT FOR CONSULTATION This Canadian Neutron Initiative (CNI) discussion paper and associated Roundtable Meeting are produced in partnership with CIFAR. We also thank the following sponsors: 2 DRAFT FOR CONSULTATION Contents 1 Executive summary and overview of a national strategy ..................................................................... 5 2 Consultation on the strategy ................................................................................................................ 9 3 The present: A strong foundation for continued excellence .............................................................. 12 3.1 The Canadian neutron beam user community ........................................................................... 12 3.2 McMaster University ................................................................................................................... 16 3.3 Other neutron beam capabilities and interests .......................................................................... 17 4 Forging foreign partnerships ............................................................................................................... 19 4.1 Global renewal of advanced neutron sources ........................................................................... -
3 Description of the Nuclear Facilities at Risø National Laboratory
Downloaded from orbit.dtu.dk on: Oct 04, 2021 Decommissioning of the nuclear facilities at Risø National Laboratory. Descriptions and cost assessment Lauridsen, K. Publication date: 2001 Document Version Publisher's PDF, also known as Version of record Link back to DTU Orbit Citation (APA): Lauridsen, K. (2001). Decommissioning of the nuclear facilities at Risø National Laboratory. Descriptions and cost assessment. Risø National Laboratory. Denmark. Forskningscenter Risoe. Risoe-R No. 1250(EN) General rights Copyright and moral rights for the publications made accessible in the public portal are retained by the authors and/or other copyright owners and it is a condition of accessing publications that users recognise and abide by the legal requirements associated with these rights. Users may download and print one copy of any publication from the public portal for the purpose of private study or research. You may not further distribute the material or use it for any profit-making activity or commercial gain You may freely distribute the URL identifying the publication in the public portal If you believe that this document breaches copyright please contact us providing details, and we will remove access to the work immediately and investigate your claim. Risø-R-1250(EN) Decommissioning of the Nuclear Facilities at Risø National Laboratory Descriptions and Cost Assessment Edited by Kurt Lauridsen Risø National Laboratory, Roskilde, Denmark February 2001 Abstract The report is the result of a project initiated by Risø National Laboratory in June 2000 on request from the Minister of Research and Information Technology. It describes the nuclear facilities at Risø National Laboratory to be decommissioned and gives an assessment of the work to be done and the costs incurred. -
The Research Reactor Irt-Sofia: 50 Years After First Criticality
E4 THE RESEARCH REACTOR IRT-SOFIA: 50 YEARS AFTER FIRST CRITICALITY K. KREZHOV International Institute for Nuclear Research and Nuclear Energy, Bulgarian Academy of Sciences, Sofia, Bulgaria Abstract The design features of the research reactor IRT-2000 in Sofia and accumulated experience in the past prior to the partial dismantling of obsolete reactor systems are outlined. The present status of the ongoing refurbishment to a low power reactor IRT-200 and its planned utilization are briefly described. 1. INTRODUCTION Since early 1956, the Bulgarian government has officially favored the use of nuclear power. In 1957 Bulgaria ratified the Statute of the IAEA and became one of the IAEA states- founders. In June 1957 the Committee for Peaceful Use of Atomic Energy (CPUAE) within the Council of Ministers was established as the specialized state body to promote the nuclear research and applications as well as to control and coordinate the related activities in industry, agriculture, medicine and science. In support to this program the research reactor (RR) IRT- Sofia was contracted. The initial construction of a reactor of the same WWR type as in Poland, Czechoslovakia, Hungary and Rumania that started in 1956 was adapted for the IRT- type of reactor designed and constructed from 1957 to 1961 by the Kurchatov Institute, Moscow. The first chain reaction was accomplished at 20:15 h on September 18, 1961. The official inauguration took place on November 9, 1961. The Reactor underwent several upgrades from initial 500 kW: 1000 kW (1962), 1500 kW (1965) and 2000 kW (IRT-2000) in 1970. The reactor was operated safely with a mixed (LEU-HEU) core for 28 years at power levels agreed upon user demands up to 2000 kW.