IAEA Nuclear Energy Series Applications of Research Reactors No
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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 -
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 -
Nuclear Medicine / PET Unit
Australasian Health Facility Guidelines Part B - Health Facility Briefing and Planning 0500 - Nuclear Medicine / PET Unit Revision 6.0 23 May 2016 Australasian Health Facility Guidelines Index 01 INTRODUCTION 4 01.01 Preamble 4 01.02 Introduction 4 01.03 Policy Framework 4 01.04 Description 5 02 PLANNING 8 02.01 Operational Models 8 02.02 Operational Policies 8 02.03 Planning Models 13 02.04 Functional Areas 14 02.05 Functional Relationships 16 03 DESIGN 17 03.01 Access 17 03.02 Parking 17 03.03 Disaster Planning 17 03.04 Infection Prevention and Control 18 03.05 Environmental Considerations 18 03.06 Space Standards and Components 18 03.07 Safety and Security 20 03.08 Finishes 21 03.09 Fixtures, Fittings & Equipment 21 03.10 Building Service Requirements 22 04 COMPONENTS OF THE UNIT 25 04.01 Standard Components 25 04.02 Non-Standard Components 25 AX APPENDICES 33 AX.01 Schedule of Accommodation 33 AX.02 Functional Relationships / Diagrams 41 AX.03 Checklists 41 AX.04 References 42 AX.05 Iodine I-131 Bedroom 42 Part B - Health Facility Briefing and Planning Page 3 0500 - Nuclear Medicine / PET Unit, Revision 6.0, 23 May 2016 Australasian Health Facility Guidelines 01 INTRODUCTION 01.01 Preamble This Health Planning Unit (HPU) has been developed for use by the design team, project managers and end users to facilitate the process of planning and design. This revision combines HPUs: 480 Positron Emission Tomography (PET) Unit and 500 Nuclear Medicine Unit which were previously provided as two separate documents. HPU 480 PET Unit will be discontinued. -
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. -
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 ........................................................................... -
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. -
Supplement Analysis for the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program
DOE/EIS-0218-SA-8 SUPPLEMENT ANALYSIS FOR THE FOREIGN RESEARCH REACTOR SPENT NUCLEAR FUEL ACCEPTANCE PROGRAM APRIL 2019 \?f1l ~ : ~ National Nuclear Security Administration U.S. Department of Energy National Nuclear Security Administration Washington, DC Supplement Analysis for the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program TABLE OF CONTENTS Page 1.0 INTRODUCTION AND BACKGROUND ........................................................................................... 1 1.1 Policy on Exemptions ..... ................................................ .... .................................................... 2 1.2 Statement of Intent Between the United States and Japan .................. .. .................... ......... 3 1.3 HEU Shipments ..... .. ............................................................................................................... 3 1.4 Training Research Isotope General Atomics (TRIGA) Fuel .................................... ................ 4 2.0 PURPOSE AND NEED, AND PROPOSED ACTION ............................................................................ 4 2.1 Purpose and Need .................................................... ...................... ....................................... 4 2.2 Proposed Action ............ .. ...................... ....................................................................... .. .... ... 4 2.3 Description of Activities ......................................................................................................... 4 3.0 AFFECTED -
Principles and Practice of PET/CT
EANMEANM® Eu ne rope edici an Association of Nuclear M Publications · Brochures Principles and Practice of PET/CT Part 1 A Technologist‘s Guide Produced with the kind Support of Editors Peter Hogg Giorgio Testanera Head of Diagnostic Imaging Research Istituto Clinico Humanitas University of Salford Department of Nuclear Medicine Salford, UK Rozzano, Italy Contributors Suzanne Dennan Ann Heathcote Department of Diagnostic Imaging Regional Manger St. James Hospital, Dublin, Ireland Alliance Medical Limited Warwick, UK Thomas Kane Consultant in Radiology & Nuclear Medicine Amy Wareing Victoria Hospital, Blackpool Senior PET CT Technologist and Lancashire PETCT Centre, Preston, UK Preston PET CT Centre Royal Preston Hospital Jean-Marc Vrigneaud Lancashire Teaching Hospitals, UK Medical Physicist Nuclear Medicine Department Peter Julyan Centre Georges-François Leclerc Clinical Scientist Dijon, France North Western Medical Physics The Christie NHS Foundation Trust, UK Sylvianne Prevot Radiation Safety O#cer Katy Szczepura Centre Georges-Francois Leclerc Medical Physics Lecturer Dijon, France Department of Diagnostic Radiography University of Salford Angela Meadows Greater Manchester, UK Unit Manager Preston PET/CT Centre Simona Cola Alliance Medical Technologist of the Department of Nuclear Royal Preston Hospital Medicine Lancashire Teaching Hospitals NHS Trust, UK S. Maria Nuova Hospital Reggio Emilia, Italy Ronald Boellaard Associate Professor and Head of Physics Department of Nuclear Medicine and PET Research VU University Medical Centre Amsterdam, The Netherlands 2 Contents Foreword Suzanne Dennan . ......................................4 Preface and Glossary of Terms and Abbreviations Peter Hogg and Giorgio Testanera . ..........................5 Chapter 1: The value and limitations of PET-CT in routine clinical practice: a UK radiologist’s perspective Thomas Kane and Peter Hogg .