Utilization of Egyptian Research Reactor and modes of collaboration
|
|
|
- Barbara Reeves
- 6 years ago
- Views:
Transcription
1 Utilization of Egyptian Research Reactor and modes of collaboration Mohamed A. GAHEEN Director of ETRR-2, Egypt TM on Research Reactor Application for Materials Under High Neutron Fluence, Vienna, November 2008
2 CONTENTS ETRR-2 Description Potential Capabilities Facilities Description Future Prospects for Utilization Modes of Collaboration
3 ETRR-2 Description ETRR-2 is a Material Testing Reactor (MTR), open pool type, 22 MW Power, of variable core arrangement, cooled and moderated by light water, with Be blocks reflectors. The reactor went critical for the first time in The reactor utilization phase started in The main aspect on the ETRR-2 design is its flexible irradiation positions and potential for modification to harmonize with the requirements of the utilization. Free access of reactor personnel and experimentalists during reactor operation at full power.
4 ETRR-2 Description Reactor core is a rectangular arrangement of up to 30 Fuel Element and the irradiation grid is variable arrangement of Be, irradiation boxes, AL blocks, or plugs. An example of core and irradiation grid arrangement is shown below.
5 ETRR-2 Description Fuel Element : - Reactor Fuel Element is MTR type with 19 fuel Plates, Low Enriched Uranium (19.75 % U 235 ), made of U 3 O 8 dispersed in pure Al matrix; - Fuel elements are Manufactured on site at the Fuel Manufacture Plant; - Reactor is re-fueled with two fresh Fuel Elements every operation cycle. Fuel Element The reactor operation cycle up to 19 full power days for high neutron fluence irradiation.
6 ETRR-2 Description Reactor Main Pool houses the reactor internal components, irradiation facilities, and beam tubes and connected to an Auxiliary Pool for spent fuel and radioactive material storage. Main Pool
7 Potential Capabilities Radioisotopes Production R & D in Physics and Engineering Neutron Activation Analysis (NAA) Semi-conductors production Material Testing Neutron Radiography Beam Tube Research and Applications Education and Training
8 Facilities Description Several experimental and production facilities are installed to meet the requirements of users for radioisotope (RI) production, Neutron Activation Analysis (NAA) applications, Neutron Transmutation Doping (NTD), neutron radiography experiments, and training of personnel. Reactor potential users are from research institutes, universities, industrial and medical organizations. Irradiation facilities: - Irradiation positions in core and irradiation grid sample irradiation and RI production; - Two positions for fast irradiation system for NAA; - Two positions in Thermal Column for NTD. Neutron Beam tubes : - Two radial beam tubes and under water beam tube; - Thermal Column; - Tangential beam tube.
9 Irradiation Facilities Thermal column Rabbit System Tow Silicon Irradiation Positions Rabbit System Core Grid Grid
10 Irradiation Facilities Sample irradiation and isotope production: - irradiation positions at the irradiation grid are 22 positions for sample irradiation for Research and Development and for isotopes production. Irradiation positions closed to core have maximum thermal flux up to 2.7x10 14 n/cm 2.sec and maximum fast flux 2.2x10 14 n/cm 2.sec; - Hot cells are installed for samples and radioisotopes (I-131, I-125, Cr-51, Ir-192 ) manipulation. Transfer Cell is for Sample/Isotope movement to/from core and send to Universal Cell for can opening and visual inspection and Sample/Isotope loading into shielded containers to RI Production Facilities; - Core center position is dedicated for Co 60 production for medical and industrial application. 50,000 Ci can be produced per year; - Co-60 Hot cell is installed for Co-60 engineering processing and sealed source production.
11 Irradiation Facilities Hot cells interconnections and connections to main and auxiliary pools
12 Material Testing Cell: - Material Testing Hot Cell is installed for Destructive Tests on irradiated samples (standard specimens ). - The cell is provided with Impact machine, Microhardness tester, and Tensile machine. - Irradiated samples are transported under water from main pool to the auxiliary pool using operational tools. - The Testing cell is connected to the Auxiliary pool, an irradiated samples carrier is used to transport irradiated samples from the Auxiliary pool to the testing cell Irradiation Facilities
13 Irradiation Facilities NAA lab: - ETRR-2 is equipped with two Fast Pneumatic Transport Systems (Rabbit Systems): One in reflector area position ( 9x10 13 n/cm 2.sec. The other being in Thermal Column position ( 2x10 11 n/cm 2.sec); - NAA lab is provided with high efficiency detection systems for elemental analysis of irradiated samples. Environmental, geological, and biological samples could be analyzed for different applications at the NAA labs with the provided detection systems; - The lab contributes to the reactor routine measurements of pools water samples, etc.
14 Irradiation Facilities Silicon Doping at ETRR-2: - Two irradiation positions at thermal column for irradiation Ingots of 28 cm long and up to 5 Inches diameter; - Thermal flux: n/cm 2 /sec and Thermal-to-fast flux ratio: Temperature during irradiation less than 80 O c; - Axial resistively variation in the product: less than 5 %; Two Silicon Irradiation Positions - Labs of post irradiation tests and measurements are also included.
15 Neutron Beam Tubes In ETRR-2, Neutron Radiography facility is Installed in front of a radial beam tube with proper shielding and samples handling mechanisms: - Beam port flux about 3.0 x10 7 n/cm 2.sec; - L= 3315 mm; - D= 30 mm. Underwater neutron radiography system has been installed for radiography examination of irradiated samples. Thermal Column and connected shielded room are dedicated for BNCT application.
16 Future Prospects for Utilization Development of the existing facilities to increase the utilization and harmonize with the market requirements: Upgrading of the NTD facilities; Introduce irradiation facilities for Mo-99 production; Installation of small angle neutron scattering (SANS) facility; Development of the static neutron radiography to be real-time to allow for more applications. Accreditation for NAA Lab and implantation of K 0 method and Large Sample AA. Start production of radio isotopes ( Cr-51, Ir-192, I-125). Continues training and re-training for manpower development to support longer time operation. Collaboration and exchange information and experience with regional countries.
17 Future Prospects for Utilization Upgrading of the NTD facilities: - it is possible to introduce modifications to the existing silicon irradiation rig to irradiate six inch diameter silicon ingots; - The existing aluminum container (about 15 mm thick) in the irradiation rig is substituted with another one of appropriate thickness (3 mm) to accommodate six-inch diameter; - A simple design of new aluminum container has been completed as well as manufacturing of one container; - The new container can irradiate larger size and quantities of doped silicon than the existing five-inch container. Irradiation tests and commissioning are in progress; - The outer positions in the irradiation grid could be mad available for irradiation of 8-inch ingots and more six-inch diameter. A simple irradiation is suggested to be adapted in ETRR-2.
18 Future Prospects for Utilization Mo-99 Production: - Two in-core irradiation boxes will be dedicated for the irradiation for production of 1000 Ci/week of Mo-99; - The in core irradiation has the advantage of no special cooling or irradiation loop is required; - The irradiation boxes will be loaded into or removed from the core while the reactor is shut down; - Co-60 Hot cell will be adapted to be used for irradiated Mo-99 targets loading into shielded containers. SANS installation at tangential beam port: The conditions are optimal for installation of 2 or 3 scattering instruments. IAEA will support a first SANS (Small Angle neutron scattering) with intermediate level for applications in material science.
19 Future Prospects for Utilization ETRR-2 irradiation facilities with modifications
20 Modes of collaboration Modes of Collaboration with other Research Reactor institutes: - Networking and bilateral co-operation; - Technical cooperation projects; - Conferences and forum; - Meetings, training activates, workshops, expert mission and scientific visits; - Experimental facilities sharing; - Common research and scientific publications; - Sharing in research projects.
21 Thank You
1. INTRODUCTION 2. EAEA EXISTING CAPABILITIES AND FACILITIES
EGYPT FINAL REPORT FOR THE CRP ON DEVELOPING TECHNIQUES FOR SMALL- SCALE, INDIGENOUS PRODUCTION OF MO-99 USING LOW- ENRICHED URANIUM (LEU) OR NEUTRON ACTIVATION 1. INTRODUCTION The Egypt country report
Institute of Atomic Energy POLATOM OTWOCK-SWIERK POLAND. Irradiations of HEU targets in MARIA RR for Mo-99 production. G.
Instytut Energii Atomowej Institute of Atomic Energy OTWOCK-SWIERK POLAND Irradiations of HEU targets in MARIA RR for Mo-99 production G. Krzysztoszek IAEA TM on Commercial Products and Services of Research
Utilization of the Irradiation Holes in HANARO
Utilization of the Irradiation Holes in HANARO Choong-Sung Lee, Guk-Hoon Ahn, In-Cheol Lim HANARO Center, Korea Atomic Energy Research Institute, Daejeon, Korea Abstract. HANARO has been used for radioisotope
Nuclear Research Reactors
Nuclear Research Reactors Seminar on Nuclear Science and Technology for Diplomats P. Adelfang (+)Division of Nuclear Fuel Cycle and Waste Technology (NEFW) Dept. of Nuclear Energy (NE) IAEA, Vienna, February
Industrial and Commercial Applications of FRM II
Industrial and Commercial Applications of FRM II Heiko Gerstenberg (and many colleagues) Forschungsneutronenquelle FRM II, Technische Universität München Campus of the TUM in Garching near Munich FRM II
1 General information and technical data of TRIGA RC-1 reactor
Contacts: Maria Grazia Iorio ENEA C.R. CASACCIA - UTFISST-REANUC - S.P. 040 via Anguillarese 301 00123 S. MARIA DI GALERIA (ROMA) mariagrazia.iorio@enea.it Link to IAEA Research Reactors Data Base: TRIGA
Budget Uncertainty and Minimum Detectable Concentrations for the INAA Laboratory of the ETRR-2
Budget Uncertainty and Minimum Detectable Concentrations for the INAA Laboratory of the ETRR2 M.Y. Khalil and Kh.. A. Elsakhawy CONTENTS Accreditation of INAA Lab What we wanted to do The ETRR2 What have
ACTIVATION ANALYSIS OF DECOMISSIONING OPERATIONS FOR RESEARCH REACTORS
ACTIVATION ANALYSIS OF DECOMISSIONING OPERATIONS FOR RESEARCH REACTORS Hernán G. Meier, Martín Brizuela, Alexis R. A. Maître and Felipe Albornoz INVAP S.E. Comandante Luis Piedra Buena 4950, 8400 San Carlos
RECH-1 RESEARCH REACTOR: PRESENT AND FUTURE APPLICATIONS
RECH-1 RESEARCH REACTOR: PRESENT AND FUTURE APPLICATIONS E.Vargas, S. Bustamante, R. Crispieri Subdepartamento de reactores Comisión Chilena de Energía Nuclear, Amunategui 95, P.O.Box 188-D, Santiago Chile
Chem 481 Lecture Material 4/22/09
Chem 481 Lecture Material 4/22/09 Nuclear Reactors Poisons The neutron population in an operating reactor is controlled by the use of poisons in the form of control rods. A poison is any substance that
The Utilisation of Australia s Research Reactor, OPAL. Kith Mendis, John Bennett and Jamie Schulz
The Utilisation of Australia s Research Reactor, OPAL Kith Mendis, John Bennett and Jamie Schulz Sydney Introducing ANSTO Centre of Australian nuclear expertise Home of Australia s only nuclear reactor
THE IAEA COLLABORATING CENTRE FOR NEUTRON ACTIVATION BASED METHODOLOGIES OF RESEARCH REACTORS
A17 THE IAEA COLLABORATING CENTRE FOR NEUTRON ACTIVATION BASED METHODOLOGIES OF RESEARCH REACTORS P. BODE Delft University of Technology, Reactor Institute Delft, Delft, The Netherlands Abstract The Reactor
DOE NNSA B&W Y-12, LLC Argonne National Lab University of Missouri INR Pitesti. IAEA Consultancy Meeting Vienna, August 24-27, 2010
Stress Analysis Finite Element Modeling DOE NNSA B&W Y-12, LLC Argonne National Lab University of Missouri INR Pitesti IAEA Consultancy Meeting Vienna, August 24-27, 2010 Target Manufacturing & Processing
Forschungs-Neutronenquelle Heinz Maier-Leibnitz (FRM II) - Overview -
Forschungs-Neutronenquelle Heinz Maier-Leibnitz (FRM II) - Overview - Outline 1. Location 2. The Reactor 3. Neutron Sources 4. Applications 1. Location 2. The Reactor 3. Neutron Sources 4. Applications
Hybrid Low-Power Research Reactor with Separable Core Concept
Hybrid Low-Power Research Reactor with Separable Core Concept S.T. Hong *, I.C.Lim, S.Y.Oh, S.B.Yum, D.H.Kim Korea Atomic Energy Research Institute (KAERI) 111, Daedeok-daero 989 beon-gil, Yuseong-gu,
JRTR Project Overview and Licensing Processes
Project Overview and Licensing Processes ANNuR/IAEA Annual Meeting on the Safety and Licensing of Research Reactors August 30, 2016 Ragai Altamimi Safety and Licensing department 1 Contents Project Overview
Portuguese Research Reactor (RPI) Exploitation and Operation
Portuguese Research Reactor (RPI) Exploitation and Operation Introduction The main task of the RPI Exploitation and Operation Group was to assure a safe and reliable operation of the reactor. With this
NEUTRON TRANSMUTATION DOPING OF SILICON: HIGHLY HOMOGENEOUS RESISTIVITY SEMICONDUCTOR MATERIAL PRODUCED IN NUCLEAR REACTORS. Artur Wilson Carbonari
NEUTRON TRANSMUTATION DOPING OF SILICON: HIGHLY HOMOGENEOUS RESISTIVITY SEMICONDUCTOR MATERIAL PRODUCED IN NUCLEAR REACTORS. Artur Wilson Carbonari Instituto de Pesquisas Energéticas e Nucleares IPEN-CNEN/SP
USA HTR NEUTRONIC CHARACTERIZATION OF THE SAFARI-1 MATERIAL TESTING REACTOR
Proceedings of HTR2008 4 th International Topical Meeting on High Temperature Reactors September 28-October 1, 2008, Washington, D.C, USA HTR2008-58155 NEUTRONIC CHARACTERIZATION OF THE SAFARI-1 MATERIAL
Proposed model for PGAA at TRIGA IPR- R1 reactor of CDTN
Proposed model for PGAA at TRIGA IPR- R1 reactor of CDTN AS LEAL, BT GUERRA, MABC Menezes, C Pereira Centre for Development of Nuclear Technology (CDTN), Brazilian Nuclear Energy Commission (CNEN), Av.
THE SLOWPOKE-2 NUCLEAR REACTOR AT THE ROYAL MILITARY COLLEGE OF CANADA: APPLICATIONS FOR THE CANADIAN ARMED FORCES
THE SLOWPOKE-2 NUCLEAR REACTOR AT THE ROYAL MILITARY COLLEGE OF CANADA: APPLICATIONS FOR THE CANADIAN ARMED FORCES P.C. Hungler 1, M. T. Andrews 1, D.G. Kelly 1 and K.S. Nielsen 1 1 Royal Military College
Neutron source: with Liquid D 2 cold neutron moderator. TRIGA = Training Research Isotopes from General Atomics. Neutron elliptical focusing reflector
Mini-Workshop, WU St. Louis, February 11, 2011 Yuri Kamyshkov/ University it of Tennessee email: kamyshkov@utk.edu Neutron source: 34MW 3.4 annular core research TRIGA reactor with Liquid D 2 cold neutron
Neutron induced reaction and neutron sources
Neutron induced reaction and neutron sources Introduction to Nuclear Science Simon Fraser University Spring 2011 NUCS 342 April 6, 2011 NUCS 342 (Lecture 29) April 6, 2011 1 / 29 Outline 1 Neutron-induced
NUCLEAR EDUCATION AND TRAINING COURSES AS A COMMERCIAL PRODUCT OF A LOW POWER RESEARCH REACTOR
NUCLEAR EDUCATION AND TRAINING COURSES AS A COMMERCIAL PRODUCT OF A LOW POWER RESEARCH REACTOR H.BÖCK, M.VILLA, G.STEINHAUSER Vienna University of Technology/Atominstitut Vienna Austria boeck@ati.ac.at
MONTE CALRLO MODELLING OF VOID COEFFICIENT OF REACTIVITY EXPERIMENT
MONTE CALRLO MODELLING OF VOID COEFFICIENT OF REACTIVITY EXPERIMENT R. KHAN, M. VILLA, H. BÖCK Vienna University of Technology Atominstitute Stadionallee 2, A-1020, Vienna, Austria ABSTRACT The Atominstitute
INDUSTRIAL AND COMMERCIAL APPLICATIONS OF FRM II 1. INTRODUCTION
INDUSTRIAL AND COMMERCIAL APPLICATIONS OF FRM II H. GERSTENBERG, A. KASTENMÜLLER, X. LI Forschungsneutronenquelle Heinz Maier-Leibnitz (FRM II), Technische Universität München, Garching, Germany heiko.gerstenberg@frm2.tum.de
Technical feasibility of producing Mo- 99 in TRIGA 14 MW reactor and associated hot cells
Technical feasibility of producing Mo- 99 in TRIGA 14 MW reactor and associated hot cells C.Toma Institute for Nuclear Research, Romania 1 OBJECTIVES - -Production of 99 Mo utilizing LEU targets in order
M.Cagnazzo Atominstitut, Vienna University of Technology Stadionallee 2, 1020 Wien, Austria
Measurements of the In-Core Neutron Flux Distribution and Energy Spectrum at the Triga Mark II Reactor of the Vienna University of Technology/Atominstitut ABSTRACT M.Cagnazzo Atominstitut, Vienna University
The Effect of 99 Mo Production on the Neutronic Safety Parameters of Research Reactors
The Effect of 99 Mo Production on the Neutronic Safety Parameters of Research Reactors Riham M. Refeat and Heba K. Louis Safety Engineering Department, Nuclear and Radiological Regulation Authority (NRRA),
Profile SFR-64 BFS-2. RUSSIA
Profile SFR-64 BFS-2 RUSSIA GENERAL INFORMATION NAME OF THE A full-scale physical model of a high-power BN-type reactor the «BFS-2» critical facility. FACILITY SHORT NAME BFS-2. SIMULATED Na, Pb, Pb-Bi,
Role of the Oarai Branch as a Facility open for University Researchers in Utilization of Research Reactors
Role of the Oarai Branch as a Facility open for University Researchers in Utilization of Research Reactors Tatsuo Shikama Institute for Materials Research, Tohoku University 2-1-1 Katahira, Aobaku, Sendai,
Nuclear Research Facilities in Russia for innovative nuclear development N. Arkhangelskiy, ROSATOM IAEA Consultancy Meeting June 2013
State Atomic Energy Corporation Rosatom Nuclear Research Facilities in Russia for innovative nuclear development N. Arkhangelskiy, ROSATOM IAEA Consultancy Meeting 10-12 June 2013 1 Introduction Russia
Reactor-physical calculations using an MCAM based MCNP model of the Training Reactor of Budapest University of Technology and Economics
Nukleon 016. december IX. évf. (016) 00 Reactor-physical calculations using an MCAM based MCNP model of the Training Reactor of Budapest University of Technology and Economics Tran Thuy Duong 1, Nguyễn
1. General information and technical data of TAPIRO research reactor
Contacts: Matteo Cesaroni ENEA C.R. CASACCIA - UTFISST-REANUC - S.P. 040 via Anguillarese 301 00123 S. MARIA DI GALERIA (ROMA) matteo.cesaroni@enea.it ENEA Casaccia TAPIRO Directors O.Fiorani A.Santagata
MYRRHA. International Symposium on Present Status and Future Perspective for Reducing Radioactive waste Tokyo, Japan October 9-10,2014
MYRRHA International Symposium on Present Status and Future Perspective for Reducing Radioactive waste Tokyo, Japan October 9-10,2014 Marc Schyns, Boeretang 200, 2400 Mol, Belgium mschyns@sckcen.be or
Idaho National Laboratory Reactor Analysis Applications of the Serpent Lattice Physics Code
Idaho National Laboratory Reactor Analysis Applications of the Serpent Lattice Physics Code By Frederick N. Gleicher II, Javier Ortensi, Benjamin Baker, and Mark DeHart Outline Intra-Pin Power and Flux
V. OPERATION AND DEVELOPMENT OF FACILITIES
V. OPERATION AND DEVELOPMENT OF FACILITIES V. OPERATION AND DEVELOPMENT OF FACILITIES 1. Kyoto University Research Reactor (KUR) Kyoto University Research Reactor (KUR) is a light-water moderated tank-type
Radioactivity of the Treated Topaz
Radioactivity of the Treated Topaz S. Salama, A.I. Helal and M.A. Gomaa Egyptian Atomic Energy Authority. ABSTRACT Raw topaz stone samples are subjected to irradiation by neutrons from the Egyptian second
NEW COMPLEX OF MODERATORS FOR CONDENSED MATTER RESEARCH AT THE IBR-2M REACTOR *
NEW COMPLEX OF MODERATORS FOR CONDENSED MATTER RESEARCH AT THE IBR-2M REACTOR * S. KULIKOV, E. SHABALIN Joint Institute for Nuclear Research, 141980, JINR, Joliot Curie 6, Dubna, Moscow reg., Russia E-mail:
Neutronic Issues and Ways to Resolve Them. P.A. Fomichenko National Research Center Kurchatov Institute Yu.P. Sukharev JSC Afrikantov OKBM,
GT-MHR Project High-Temperature Reactor Neutronic Issues and Ways to Resolve Them P.A. Fomichenko National Research Center Kurchatov Institute Yu.P. Sukharev JSC Afrikantov OKBM, GT-MHR PROJECT MISSION
SLOWPOKE-2 31 YEARS AND STILL GLOWING
Slide 1 SLOWPOKE-2 31 YEARS AND STILL GLOWING Canadian Nuclear Society Conference 2012 Slide 2 SRC s SLOWPOKE-2 Reactor 31 Years and Still Glowing Slide 3 Safe LOW POWer Kritical Experiment Slowpoke is
Design of an Integrated Inspection System For Detection of Explosive and Illicit Materials
Design of an Integrated Inspection System For Detection of Explosive and Illicit Materials IAEA 2 nd CRP Meeting, Mumbai, 12 16 November 2007 R. M. Megahid Nuclear Research Centre, Atomic Energy Authority
Aluminum Half-Life Experiment
Aluminum Half-Life Experiment Definition of half-life (t ½ ): The half-life of any declining population is the time required for the population to decrease by a factor of 50%. Radioactive isotopes represent
Int. Coaf. Physics of Nuclear Science and Technology
BNL-6 5 2 43 Int. Coaf. Physics of Nuclear Science and Technology October S-8, 1998 RADIATION DOSIMETRY AT THE BNL HIGH FLUX BEAM REACTOR* NE Holden', J-P Hu', RN Reciniello* 1. Reactor Division, Brookhaven
IPEN-CNEN/SP. F. A. Genezini 1, A. J. Fernando 1, A. Marra Neto 1, P. E. Aoki 2, W. A. P. Calvo 2
F. A. Genezini 1, A. J. Fernando 1, A. Marra Neto 1, P. E. Aoki 2, W. A. P. Calvo 2 National Nuclear Energy Commission - Nuclear and Energy Research Institute Nuclear 1 Nuclear and Energy Research Research
Status of J-PARC Transmutation Experimental Facility
Status of J-PARC Transmutation Experimental Facility 10 th OECD/NEA Information Exchange Meeting for Actinide and Fission Product Partitioning and Transmutation 2008.10.9 Japan Atomic Energy Agency Toshinobu
MEASUREMENT OF SPENT FUEL ASSEMBLIES IN SPRR-300
MEASUREMENT OF SPENT FUEL ASSEMBLIES IN SPRR-300 CHEN Wei, HU Zhiyong, YANG Rui Institute of Nuclear Physics and Chemistry, Sichuan, China 1 Preface SPRR-300 is a pool-typed research reactor which uses
Study of irradiation effects in materials with high-neutron-flux fission reactors
Study of irradiation effects in materials with high-neutron-flux fission reactors Tatsuo Shikama Tohoku University 2-1-1Katahira, Aobaku, Sendai, 980-8577 Japan shikama@imr.tohoku.ac.jp The Oarai Branch,
LVR-15 Reactor Application for Material Testing. Nuclear Research Institute Řež,, plc Reactor Services Division
LVR-15 Reactor Application for Material Testing M. Marek,, J.Kysela Kysela,, J.Burian Nuclear Research Institute Řež,, plc Reactor Services Division Research Reactor LVR-15 Light-water moderated and cooled
Neutronic Calculations of Ghana Research Reactor-1 LEU Core
Neutronic Calculations of Ghana Research Reactor-1 LEU Core Manowogbor VC*, Odoi HC and Abrefah RG Department of Nuclear Engineering, School of Nuclear Allied Sciences, University of Ghana Commentary Received
Reactivity Power and Temperature Coefficients Determination of the TRR
Reactivity and Temperature Coefficients Determination of the TRR ABSTRACT Ahmad Lashkari Nuclear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran Tehran 14399-51113,
12/18/2016. Radioanalysis Laboratory Capabilities and Issues. Eleventh Annual Radiation Measurement Cross Calibration Workshop RMCC XI
1. Introduction 2. Laboratories Gamma spectrometry laboratory. Radiochemistry laboratory. Analytical chemistry laboratory. Alpha spectrometry laboratory Gross alpha / beta laboratory. Neutron activation
Application of the next generation of the OSCAR code system to the ETRR-2 multi-cycle depletion benchmark
Application of the next generation of the OSCAR code system to the ETRR-2 multi-cycle depletion benchmark M. Mashau 1, S.A. Groenewald 1, F.A. van Heerden 1 1) The South African Nuclear Energy Corporation
Center for Design and Synthesis of Radiopharmaceuticals for Molecular Targeting CERAD on the Polish Roadmap for Research Infrastructures
Center for Design and Synthesis of Radiopharmaceuticals for Molecular Targeting CERAD on the Polish Roadmap for Research Infrastructures Renata Mikolajczak National Centre for Nuclear Research, Warsaw,
Implementation of the NPT Safeguards Agreement in the Republic of Korea
International Atomic Energy Agency Board of Governors GOV/2004/84 Date: 11 November 2004 Restricted Distribution Original: English For official use only Item 4(c) of the provisional agenda (GOV/2004/82)
The High Flux Isotope Reactor Past, Present, and Future M. B. Farrar K. J. Beierschmitt
The High Flux Isotope Reactor Past, Present, and Future M. B. Farrar K. J. Beierschmitt Following the conclusion of World War II and through the 1950s, nuclear science and engineering enjoyed an extraordinary
THE CONTRIBUTION OF HANARO TO THE R&D RELEVANT TO THE SMART AND VHTR SYSTEM
THE CONTRIBUTION OF HANARO TO THE R&D RELEVANT TO THE SMART AND VHTR SYSTEM K.N. CHOO, M.S. CHO, J.S. PARK, W.J. LEE, I.C. LIM, J.J. HA Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Neutronic design of the ESS targetmoderatorreflector. Luca Zanini For the ESS target division and in-kind collaborators
Neutronic design of the ESS targetmoderatorreflector system Luca Zanini For the ESS target division and in-kind collaborators Nordic-Gen4 seminar, Risoe, 29-31 October 2012 ESS timeline On schedule for
JHR PROJECT. IRRADIATION DEVICES IN-SERVICE INSPECTION OF NUCLEAR PRESSURE EQUIPMENT S.
JHR PROJECT. IRRADIATION DEVICES IN-SERVICE INSPECTION OF NUCLEAR PRESSURE EQUIPMENT S. Investigation of Non DESTRUCTIVE EXAMINATIONS For INSPECTION Purposes. S.Gaillot CEA-France IGORR 18 & IAEA Workshop
This article appeared in a journal published by Elsevier. The attached copy is furnished to the author for internal non-commercial research and
This article appeared in a journal published by Elsevier. The attached copy is furnished to the author for internal non-commercial research and education use, including for instruction at the authors institution
Neutronics experiments for validation of activation and neutron transport data for fusion application at the DT neutron generator of TU Dresden
Neutronics experiments for validation of activation and neutron transport data for fusion application at the DT neutron generator of TU Dresden A. Klix1, A. Domula2, U. Fischer1, D. Gehre2 1 Karlsruhe
Mushtaq Ahmad Isotope Production Division Pakistan Institute of Nuclear Science and Technology (PINSTECH) Islamabad, PAKISTAN
Mushtaq Ahmad Isotope Production Division Pakistan Institute of Nuclear Science and Technology (PINSTECH) Islamabad, PAKISTAN Abstrct Both reactors (Pakistan Research Reactor 1 and Pakistan Research Reactor-2)
Major Nuclear and Radiation Physics experimental facilities in. Prepared By Dr M Tanseer Ali
Major Nuclear and Radiation Physics experimental facilities in Prepared By Dr M Tanseer Ali Research Facilities Atomic Energy Centre (AECD), Dhaka Ministry of Science and Technology Atomic Energy Research
Invariability of neutron flux in internal and external irradiation sites in MNSRs for both HEU and LEU cores
Indian Journal of Pure & Applied Physics Vol. 49, February 2011, pp. 83-90 Invariability of neutron flux in internal and external irradiation sites in MNSRs for both HEU and LEU cores M Albarhoum Department
Quality control of neutron-absorber materials for the nuclear fuel cycle, Principle of the JEN-3 neutron Backscattering gauge
Quality control of neutron-absorber materials for the nuclear fuel cycle, Principle of the JEN-3 neutron Backscattering gauge Hamid MAKIL (CEADRT/LIST/LCAE) Patrick BRISSET (IAEA) ICARST 2017, 24 28 April
MEASUREMENT AND COMPARISON OF CONTROL ROD WORTH OF BTRR USING INHOUR EQUATION AND PERIOD REACTIVITY CONVERSION TABLE
J. Bangladesh Acad. Sci., Vol. 41, No. 1, 95-103, 2017 MEASUREMENT AND COMPARISON OF CONTROL ROD WORTH OF BTRR USING INHOUR EQUATION AND PERIOD REACTIVITY CONVERSION TABLE MD. IQBAL HOSAN, M. A. M. SONER
at Oak Ridge National Laboratory.
361 Designs for Neutron Radiography at Oak Ridge National Laboratory and Computed Tomography Dudley A. Raine lipv4, Camden R. Hubbard, Paul M. Whaley, and Michael C. Wright3 Oak Ridge National Laboratory
Development of education and training programs using ISIS research reactor
Development of education and training programs using ISIS research reactor F. Foulon 1, B. Lescop 1, X. Wohleber 2 1) National Institute for Nuclear Science and Technology, CEA-Saclay,France 2) Nuclear
I-4. SANS BATAN: Improvement the Neutron Intensity by Focusing Optics
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
PRESENT SERVICES AT THE TRIGA MARK II REACTOR OF THE JSI
PRESENT SERVICES AT THE TRIGA MARK II REACTOR OF THE JSI B. SMODIŠ, L. SNOJ Jožef Stefan Institute, Ljubljana, Slovenia borut.smodis@ijs.si 1. INTRODUCTION IAEA-TM-38728 (2010) The 250 kw TRIGA Mark II
PoS(FNDA2006)033. Radiography Using Fission Neutrons. Thomas Bücherl. Christoph Lierse von Gostomski
Radiography Using Fission Neutrons Institut für Radiochemie, Technische Universität München Wlather-Meissner-Str. 3, 85748 Garching, Germany E-mail: Thomas.buecherl@radiochemie.de Christoph Lierse von
Fuel Element Burnup Determination in HEU - LEU Mixed TRIGA Research Reactor Core
Fuel Element Burnup Determination in HEU - LEU Mixed TRIGA Research Reactor Core Tomaž Žagar, Matjaž Ravnik Institute "Jožef Stefan", Jamova 39, Ljubljana, Slovenia Tomaz.Zagar@ijs.si Abstract This paper
Correction of the electric resistivity distribution of Si wafers using selective neutron transmutation doping (SNTD) in MARIA nuclear research reactor
NUKLEONIKA 2012;57(3):363 367 ORIGINAL PAPER Correction of the electric resistivity distribution of Si wafers using selective neutron transmutation doping (SNTD) in MARIA nuclear research reactor Mikołaj
New irradiation zones at the CERN-PS
Nuclear Instruments and Methods in Physics Research A 426 (1999) 72 77 New irradiation zones at the CERN-PS M. Glaser, L. Durieu, F. Lemeilleur *, M. Tavlet, C. Leroy, P. Roy ROSE/RD48 Collaboration CERN,
WM 07 Conference, February 25 March 01, 2007, Tucson, AZ
Design and Construction of a High Energy X-Ray R&D Facility, and the Development and Optimization of Real Time Radioisotopic Characterization of Remote Handled Waste at MeV Energies. S. Halliwell, V.J.Technologies
Measurement of Average Thermal Neutron Flux for PGNAA Setup
2017 IJSRST Volume 3 Issue 8 Print ISSN: 2395-6011 Online ISSN: 2395-602X Themed Section: Science and Technology Measurement of Average Thermal Neutron Flux for PGNAA Setup Dalpat Meena 1, S. K. Gupta
The PSI Hotlab Who we are and what we do NES Event
WIR SCHAFFEN WISSEN HEUTE FÜR MORGEN Marco Streit :: NES / AHL The PSI Hotlab Who we are and what we do Highlights @ NES Event 24.10.2017 Facts & Figures of PSI Hotlab Built 1961 1963 (11 Mio CHF) Continuously
Efficient Utilization of a Low-Power Research Reactor
Efficient Utilization of a Low-Power Research Reactor Technical Meeting on the Role of Universities in Preserving and Managing Nuclear Knowledge IAEA, 10-14.12. 14.12. 2007 H.Böck boeck@ati.ac.at M.Villa
SCANNING OF CARGO CONTAINERS BY GAMMA-RAY AND FAST NEUTRON RADIOGRAPHY
Armenian Journal of Physics, 2012, vol. 5, issue 1, pp. 1-7 SCANNING OF CARGO CONTAINERS BY GAMMA-RAY AND FAST NEUTRON RADIOGRAPHY A. M. Yousri*, A. M. Osman, W. A. Kansouh, A. M. Reda*, I. I. Bashter*,
Facilities Management
Policy Number: 700.20 Title: Chemical Fume Hood Policy Implementation Date: 2002 Last Audited: August, 2017 Last Revised: October 23rd, 2017 Facilities Management Introduction The laboratory chemical fume
PARAMETERISATION OF FISSION NEUTRON SPECTRA (TRIGA REACTOR) FOR NEUTRON ACTIVATION WITHOUT THE USED OF STANDARD
Parameterisation of Fission Neutron Spectra (TRIGA Reactor) 81 7 PARAMETERISATION OF FISSION NEUTRON SPECTRA (TRIGA REACTOR) FOR NEUTRON ACTIVATION WITHOUT THE USED OF STANDARD Liew Hwi Fen Noorddin Ibrahim
COMMISSIONING TESTS OF THE NEW NEUTRON RADIOGRAPHY FACILITY AT THE LVR-15 REACTOR ABSTRACT
COMMISSIONING TESTS OF THE NEW NEUTRON RADIOGRAPHY FACILITY AT THE LVR-15 REACTOR J. ŠOLTÉS, L. VIERERBL Neutron Physics Department, Research Centre Rez Ltd., Hlavní 130, 250 68 Husinec-Řež, Czech Republic
Applications of MCBEND
Serco Assurance Applications of MCBEND Presentation to NPL Workshop on Monte Carlo codes by Pat Cowan The ANSWERS Software Service Serco Assurance Overview The MCBEND Code Traditional Applications Industrial
Los Alamos National Laboratory Facility Review
Los Alamos National Laboratory Facility Review Ron Nelson P-27 & LANSCE Neutron Data Needs & Capabilities for Applications LBNL 27 May 2015 Los Alamos Neutron Science Center User Facilities Los Alamos
Three-dimensional RAMA Fluence Methodology Benchmarking. TransWare Enterprises Inc., 5450 Thornwood Dr., Suite M, San Jose, CA
Three-dimensional RAMA Fluence Methodology Benchmarking Steven P. Baker * 1, Robert G. Carter 2, Kenneth E. Watkins 1, Dean B. Jones 1 1 TransWare Enterprises Inc., 5450 Thornwood Dr., Suite M, San Jose,
MA/LLFP Transmutation Experiment Options in the Future Monju Core
MA/LLFP Transmutation Experiment Options in the Future Monju Core Akihiro KITANO 1, Hiroshi NISHI 1*, Junichi ISHIBASHI 1 and Mitsuaki YAMAOKA 2 1 International Cooperation and Technology Development Center,
An overview for the SPES-BNCT project, proposed some years ago by Legnaro Labs, is given in such a presentation. The project aims at constructing an
An overview for the SPES-BNCT project, proposed some years ago by Legnaro Labs, is given in such a presentation. The project aims at constructing an accelerator-based, high-intensity, thermal neutron beam
Measurement of the Westcott Conventionality Thermal Neutron Flux and Suchlike at Irradiation Facilities of the KUR
Measurement of e Westcott Conventionality Thermal Neutron Flux and Suchlike at Irradiation Facilities of e KUR Hiroshi CHATANI Research Reactor Institute, Kyoto University Kumatori-cho, Sennan-gun, Osaka
The Lead-Based VENUS-F Facility: Status of the FREYA Project
EPJ Web of Conferences 106, 06004 (2016) DOI: 10.1051/epjconf/201610606004 C Owned by the authors, published by EDP Sciences, 2016 The Lead-Based VENUS-F Facility: Status of the FREYA Project Anatoly Kochetkov
Typical Safety Analysis Application for a Nuclear Research Reactor
International Conference Nuclear Energy for New Europe 2006 Portorož, Slovenia, September 18-21, 2006 http://www.djs.si/port2006 Typical Safety Analysis Application for a Nuclear Research Reactor ABSTRACT
Task 3 Desired Stakeholder Outcomes
Task 3 Desired Stakeholder Outcomes Colby Jensen IRP Kickoff Meeting, Nov 19-20, 2015 Instrumentation Overview Three general levels of core instrumentation: Reactor control and operation Additional reactor
Neutron Imaging System For level Interface Measurement
Malaysia International NDT Conference & Exhibition 2015 (MINDTCE-15), Nov 22-24 - www.ndt.net/app.mindtce-15 Neutron Imaging System For level Interface Measurement More Info at Open Access Database www.ndt.net/?id=18667
A Project for High Fluence 14 MeV Neutron Source
A Project for High Fluence 14 MeV Neutron Source Mario Pillon 1, Maurizio Angelone 1, Aldo Pizzuto 1, Antonino Pietropaolo 1 1 Associazione ENEA-EURATOM Sulla Fusione, ENEA C.R. Frascati, via E. Fermi,
Evaluation of Radiation Characteristics of Spent RBMK-1500 Nuclear Fuel Storage Casks during Very Long Term Storage
SESSION 7: Research and Development Required to Deliver an Integrated Approach Evaluation of Radiation Characteristics of Spent RBMK-1500 Nuclear Fuel Storage Casks during Very Long Term Storage A. Šmaižys,
DEVELOPMENT OF REAL-TIME FUEL MANAGEMENT CAPABILITY AT THE TEXAS A&M NUCLEAR SCIENCE CENTER
DEVELOPMENT OF REAL-TIME FUEL MANAGEMENT CAPABILITY AT THE TEXAS A&M NUCLEAR SCIENCE CENTER A Thesis by NEIL AUBREY PARHAM Submitted to the Office of Graduate Studies of Texas A&M University in partial
Malaysian Small Angle Neutron Scattering (mysans)
Malaysian Small Angle Neutron Scattering (mysans) Agensi Nuklear Malaysia Introduction - RTP Reaktor TRIGA PUSPATI (RTP) NR 1 MW tangential SANS RTP - Beamports SANS PGNAA* BCNT* NR ND* *not yet Members
Communication Received from France Concerning Its Policies Regarding the Management of Plutonium
Information Circular INFCIRC/549/Add.5/21 Date: 29 September 2017 General Distribution Original: French Communication Received from France Concerning Its Policies Regarding the Management of Plutonium
Design and production of Scintillation Detectors
Design and production of Scintillation Detectors Components for nuclear radiation detectors Fields of application: * Medicine * Industry * Science * Security Scintillation Detectors : Instruments using
DETAILED CORE DESIGN AND FLOW COOLANT CONDITIONS FOR NEUTRON FLUX MAXIMIZATION IN RESEARCH REACTORS
Proceedings of ICONE14 14th International Conference on Nuclear Engineering June 17-21, 2006, Miami, FL, USA ICONE14-89547 DETAILED CORE DESIGN AND FLOW COOLANT CONDITIONS FOR NEUTRON FLUX MAXIMIZATION
2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea
Neutronic evaluation of thorium-uranium fuel in heavy water research reactor HADI SHAMORADIFAR 1,*, BEHZAD TEIMURI 2, PARVIZ PARVARESH 1, SAEED MOHAMMADI 1 1 Department of Nuclear physics, Payame Noor