Belarus activity in ADS field
|
|
- Gyles Lucas
- 6 years ago
- Views:
Transcription
1 Joint Institute for Power&Nuclear Research-Sosny National Academy of Sciences of Belarus Belarus activity in ADS field H. Kiyavitskaya, Yu. Fokov, Ch. Routkovskaya, V. Bournos, S. Sadovich, S. Mazanik, I. Edchik, A. Kulikovskaya (YALINA team) 45 th IAEA Meting TWG-FR, ANL, USA, June 2012
2 Content Introduction International cooperation YALINA facility YALINA Booster assembly Obtained experience Conclusion
3 Introduction IAEA Coordinated Research Project (CRP) on Analytical and Experimental Benchmark Analysis of Accelerator Driven Systems Contract N /R The YALINA-Thermal and YALINA-Booster benchmarks IAEA CRP Low Enriched Uranium Fuel Utilization in Accelerator Driven Sub- Critical Assembly Systems
4 Introduction (cont.) State program scientific investigations Nuclear Power, Nuclear and Radiation Technologies State program Scientific support of the development of nuclear power in the Republic of Belarus
5 International cooperation ISTC Projects B070 (EC), B1341 (USA), B1732P (USA) IP EUROTRANS EU Framework Programs The objectives of the ISTC Project #B1732P in collaboration with USA are: To use LEU fuel instead of HEU for the YALINA-Booster assembly; To evaluate the consequences of converting to LEU fuel (by enrichment <20%); To examine possible ways to maintain the original performance with HEU.
6 The YALINA facility: To develop the experimental techniques and adapt the existing ones for monitoring the sub-criticality level, neutron spectra measurements, etc; To study the spatial kinetics of sub-critical systems driven by external neutron sources; To study the maintenance and operating performance of ADS; To measure the transmutation reaction rates of minor-actinides and long-lived fission products.
7 YALINA facility
8 YALINA-Booster sub-critical assembly (to the left), neutron generator (to the right)
9 The ISTC Projects #B1341 and B1732P the experimental and theoretical studies were carried out to define the sub-critical YALINA-Booster performance in original configuration with 90% Umet+36% UO2 in fast zone and 10% UO2 in thermal zone the experimental and theoretical studies at configuration of YALINA-Booster with 36% UO2 in fast zone and 10% UO2 in thermal zone the experimental and theoretical studies at configuration of YALINA-Booster with 21% UO2 in fast zone and 10% UO2 in thermal zone (JIPNR-configuration) the experimental and theoretical studies at configuration of YALINA-Booster with 21% UO2 in fast zone and 10% UO2 in thermal zone (ANL configuration)
10 Fast zone of the YALINA-Booster assembly (rectangular and rounded geometry) D E F G H I D E F G H I EC1B 5 EC1B 6 EC2B 6 EC2B EC4B 8 EC4B EC3B EC3B 9 9 Ionguide Problem fuel channels (18) Absorber zone, 108 rods with Umet. (nat.) Absorber zone, 116 rods with B4C Fuel rods with UO 2, 21% enrichment by U-235 (601) Empty fuel channels (76) EC1B-EC3B - experimental channels in fast zone EC4B - experimental channel in fast zone Ionguide Absorber zone, 108 rods with Umet. (nat.) Absorber zone, 116 rods with B4C Fuel rods with UO 2, 21% enrichment by U-235 (595) Empty and problem fuel channels (100) sealed by hermetical SS tubes EC1B-EC3B - experimental channels in fast zone EC4B - experimental channel in fast zone
11 The obtained experience: The replacement of the 90% enriched metallic uranium fuel in the inner region of the fast zone by 36 % (first) and 21% (second) enriched uranium dioxide reduces the contribution of fast zone to the total reactivity of the assembly, softens slightly the neutron spectrum in the fast zone. The neutron spectrum in the thermal zone remains unchanged.
12 Conclusions The YALINA facility is a unique installation which was designed as a zero power model of real ADS. It is intended to study neutronics and kinetics of the sub-critical reactors driven by external neutron sources. The successful operation of this facility is a scientific contribution from the Republic of Belarus, as well as the international team from EC and USA. The experimental data are used to benchmark and validate methods and computer codes for designing and licensing ADS.
13 The facility generated valuable data in the following areas: investigation of spatial kinetics of the sub-critical systems with external neutron sources; validation of the experimental techniques for, e.g., sub-criticality monitoring, etc; estimation of probability of minor actinides and fission products transmutation; nuclear and radiation safety analyses of sub-critical systems driven by external neutron sources; neutron activation analysis; utilization of low enriched uranium fuel for studying accelerator driven sub-critical systems.
14 The YALINA-Booster experiments performed during and after the conversion of fast zone HEU fuel to use the fuel with reduced uranium enrichment reached the following conclusions: The assembly has a strong heterogeneity affecting the spatial kinetics; The interface (absorber) zone between the fast and thermal zone has clear impact on the assembly performance; the kinetic parameters (neutron generation time, effective fraction of delayed neutrons, etc.) are defined by the thermal zone; the experimental results obtained with application of PNS area method improves as the effective multiplication factor exceeds 0.8. The delayed neutron fraction value is used based on the MCNP simulation and it needs experimental verification;
15 The YALINA-Booster experiments performed during and after the conversion of fast zone HEU fuel to use the fuel with reduced uranium enrichment reached the following conclusions: The discrepancy between the experimental (PNS method) and calculated effective multiplication factor is less than 1 % without eliminating the spatial effects. After the replacement of the 90% enriched metallic uranium by 36% UO2 in the inner region of the fast zone, some additional amount of nuclear fuel was added into thermal zone to maintain keff at the proper level. The main YALINA-Booster neutronics was not affected remarkably, only the neutron spectrum softened slightly in the inner region of the fast zone.
16 The YALINA-Booster experiments performed during and after the conversion of fast zone HEU fuel to use the fuel with reduced uranium enrichment reached the following conclusions: As it was expected the second step of the conversion to LEU fuel (to 21% UO2 in fast zone) resulted in significant reduction of the effective multiplication factor. The value of keff estimated by MCNP was about 0.963, the experimental one Despite the lack of additional fuel, there was a chance to maintain the assembly s performance consisted in changing the geometry of fast and absorber zone. The ANL proposed to realize the rounded configurations of these zones in the framework of the ISTC Project B1732P. The changes were introduced, the assembly was put into operation and the planned experiments were performed. The results are being processed just now. It should be noted that new configuration of fast zone has a great potential to keep the performance of the assembly s old configuration with HEU fuel.
17 New proposal is under discussion with ANL, USA Subcritical assembly fast neutron spectrum low enriched uranium fuel (< 20% X 5 ) Neutron generator as an external neutron source In cooperation and support ANL and IAEA
18 Thank you very much
The investigations in the field of advanced nuclear power systems for energy production and transmutation of RAW in NAS of Belarus
The investigations in the field of advanced nuclear power systems for energy production and transmutation of RAW in NAS of Belarus on behalf of YALINA team Dr. Kiyavitskaya H. ISTC meeting «Feature technology:
More informationReactivity Monitoring with Imposed Beam Trips and Pulsed Mode Detectors in the Subcritical Experiment YALINA-Booster
1 ADS/P4-08 Reactivity Monitoring with Imposed Beam Trips and Pulsed Mode Detectors in the Subcritical Experiment YALINA-Booster V. Bécares Palacios 1, M. Fernández Ordóñez 1, D. Villamarín 1, E. M. González
More informationYALINA-Booster Conversion Project
1 ADS/ET-06 YALINA-Booster Conversion Project Y. Gohar 1, I. Bolshinsky 2, G. Aliberti 1, F. Kondev 1, D. Smith 1, A. Talamo 1, Z. Zhong 1, H. Kiyavitskaya 3,V. Bournos 3, Y. Fokov 3, C. Routkovskaya 3,
More informationReactivity monitoring of a subcritical assembly using beam-trips and current-mode fission chambers: The Yalina-Booster program
1 ADS/ET-4 Reactivity monitoring of a subcritical assembly using beam-trips and current-mode fission chambers: The Yalina-Booster program M. Fernández-Ordóñez 1, D. Villamarín 1, V. Bécares 1, E.M. González-Romero
More informationJoint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies May Transmutation Systems
2141-4 Joint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies 3-14 May 2010 Transmutation Systems Stanculescu A. IAEA Vienna AUSTRIA R&D IN THE FIELD OF ACCELERATOR DRIVEN
More informationDivision of Nuclear Fission, CIEMAT, Avenida Complutense 40, Madrid, Spain
Science and Technology of Nuclear Installations Volume 212, Article ID 24693, 7 pages doi:1.1155/212/24693 Research Article Detector Dead Time Determination and Optimal Counting Rate for a Detector Near
More informationThe 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
More informationBenchmark Experiments of Accelerator Driven Systems (ADS) in Kyoto University Critical Assembly (KUCA)
Benchmark Experiments of Accelerator Driven Systems (ADS) in Kyoto University Critical Assembly (KUCA) C. H. Pyeon, T. Misawa, H. Unesaki, K. Mishima and S. Shiroya (Kyoto University Research Reactor Institute,
More informationNeutronic 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
More informationReactivity Assessment in Subcritical Systems CARL-MAGNUS PERSSON
Reactivity Assessment in Subcritical Systems CARL-MAGNUS PERSSON Licentiate Thesis in Physics Stockholm, Sweden 2007 TRITA-FYS 2007:13 ISSN 0280-316X ISRN KTH/FYS/--07:13--SE ISBN 978-91-7178-611-1 KTH
More informationInstitute 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
More informationUSA 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
More informationFuel 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
More informationReactor Physics Calculations for a Sub critical Core of the IPEN-MB-01 driven by an external neutron source
2007 International Nuclear Atlantic Conference - INAC 2007 Santos, SP, Brazil, September 30 to October 5, 2007 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-02-1 Reactor Physics Calculations
More informationMUSE-4 BENCHMARK CALCULATIONS USING MCNP-4C AND DIFFERENT NUCLEAR DATA LIBRARIES
MUSE-4 BENCHMARK CALCULATIONS USING MCNP-4C AND DIFFERENT NUCLEAR DATA LIBRARIES Nadia Messaoudi and Edouard Mbala Malambu SCK CEN Boeretang 200, B-2400 Mol, Belgium Email: nmessaou@sckcen.be Abstract
More informationError Estimation for ADS Nuclear Properties by using Nuclear Data Covariances
Error Estimation for ADS Nuclear Properties by using Nuclear Data Covariances Kasufumi TSUJIMOTO Center for Proton Accelerator Facilities, Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken
More information1. 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
More informationCRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH UO 2 GD 2 O 3 BURNABLE POISON RODS
CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH UO 2 GD 2 O 3 BURNABLE POISON RODS Alfredo Abe 1, Rinaldo Fuga 1, Adimir dos Santos 2, Graciete S. de Andrade e Silva 2, Leda C. C. B. Fanaro
More informationNeutronic 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
More informationOperational Reactor Safety
Operational Reactor Safety 22.091/22.903 Professor Andrew C. Kadak Professor of the Practice Lecture 3 Reactor Kinetics and Control Page 1 Topics to Be Covered Time Dependent Diffusion Equation Prompt
More informationD. Cano Ott Nuclear Innovation Nuclear Fission Division Dept. of Energy. CIEMAT-IFIC-UPC collaboration
Beta-delayed neutron measurements for nuclear technologies D. Cano Ott Nuclear Innovation Nuclear Fission Division Dept. of Energy CIEMAT-IFIC-UPC collaboration i i B i GT K f i I ( Z, Q i ) T 1/ 2 K 1
More informationStudy on SiC Components to Improve the Neutron Economy in HTGR
Study on SiC Components to Improve the Neutron Economy in HTGR Piyatida TRINURUK and Assoc.Prof.Dr. Toru OBARA Department of Nuclear Engineering Research Laboratory for Nuclear Reactors Tokyo Institute
More informationFundamentals of Nuclear Reactor Physics
Fundamentals of Nuclear Reactor Physics E. E. Lewis Professor of Mechanical Engineering McCormick School of Engineering and Applied Science Northwestern University AMSTERDAM BOSTON HEIDELBERG LONDON NEW
More informationPower Installations based on Activated Nuclear Reactions of Fission and Synthesis
Yu.V. Grigoriev 1,2, A.V. Novikov-Borodin 1 1 Institute for Nuclear Research RAS, Moscow, Russia 2 Joint Institute for Nuclear Research, Dubna, Russia Power Installations based on Activated Nuclear Reactions
More informationNuclear waste management
Nuclear waste management Permanent staff : G. Ban, F-R. Lecolley, J-L. Lecouey, G. Lehaut, N. Marie-Nourry, J-C. Steckmeyer Emeritus : J-F. Lecolley PhD student: H-E. Thyebault Collaborations : LPSC Grenoble,
More informationSTEK experiment Opportunity for Validation of Fission Products Nuclear Data
STEK experiment Opportunity for Validation of Fission Products Nuclear Data Dirceu F. da Cruz Nuclear Research and Consultancy Group NRG, Petten, The Netherlands November 27 th 2014 Outline Introduction
More informationVERIFICATION OFENDF/B-VII.0, ENDF/B-VII.1 AND JENDL-4.0 NUCLEAR DATA LIBRARIES FOR CRITICALITY CALCULATIONS USING NEA/NSC BENCHMARKS
VERIFICATION OFENDF/B-VII.0, ENDF/B-VII.1 AND JENDL-4.0 NUCLEAR DATA LIBRARIES FOR CRITICALITY CALCULATIONS USING NEA/NSC BENCHMARKS Amine Bouhaddane 1, Gabriel Farkas 1, Ján Haščík 1, Vladimír Slugeň
More informationQuiz, Physics & Chemistry
Eight Sessions 1. Pressurized Water Reactor 2. Quiz, Thermodynamics & HTFF 3. Quiz, Physics & Chemistry 4. Exam #1, Electrical Concepts & Systems 5. Quiz, Materials Science 6. Quiz, Strength of Materials
More informationExperiments using transmutation set-ups. Speaker : Wolfram Westmeier for
Novi Sad, ad hoc Experiments using transmutation set-ups Speaker : Wolfram Westmeier for Participants of collaboration are JINR members or they have Agreements : Russia, Germany, Armenia, Australia, Belarus,
More informationAdaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source
Adaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source E. Hoffman, W. Stacey, G. Kessler, D. Ulevich, J. Mandrekas, A. Mauer, C. Kirby, D. Stopp, J. Noble
More informationHybrid 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,
More informationReactivity monitoring using the Area method for the subcritical VENUS-F core within the framework of the FREYA project
Reactivity monitoring using the Area method for the subcritical VENUS-F core within the framework of the FREYA project N. Marie 1, G. Lehaut 1, J.-L. Lecouey 1, A. Billebaud 2, S. Chabod 2, X. Doligez
More informationStatus 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
More informationAnalysis of the TRIGA Reactor Benchmarks with TRIPOLI 4.4
BSTRCT nalysis of the TRIG Reactor Benchmarks with TRIPOLI 4.4 Romain Henry Jožef Stefan Institute Jamova 39 SI-1000 Ljubljana, Slovenia romain.henry@ijs.si Luka Snoj, ndrej Trkov luka.snoj@ijs.si, andrej.trkov@ijs.si
More informationThe MYRRHA ADS project
The MYRRHA ADS project Paul Schuurmans for the MYRRHA Team High Level Nuclear Waste Fuel fission U 235 n Actinides Minor Actinides n Uranium Fission n Neutron n Pu Np Am Cm U 238 U 235 U 238 Plutonium
More informationA TEMPERATURE DEPENDENT ENDF/B-VI.8 ACE LIBRARY FOR UO2, THO2, ZIRC4, SS AISI-348, H2O, B4C AND AG-IN-CD
2009 International Nuclear Atlantic Conference - INAC 2009 Rio de Janeiro,RJ, Brazil, September27 to October 2, 2009 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-03-8 A TEMPERATURE
More informationPrompt Alpha Calculation With Monte Carlo Code JMCT
Prompt Alpha Calculation With Monte Carlo Code JMCT Rui LI 1,2, Tao YE 1, Gang LI 1,2 *, Yun BAI 1, Li DENG 1,2 1 Institute of Applied Physics and Computational Mathematics(IAPCM): FengHao East Road No.2,
More informationFuel cycle studies on minor actinide transmutation in Generation IV fast reactors
Fuel cycle studies on minor actinide transmutation in Generation IV fast reactors M. Halász, M. Szieberth, S. Fehér Budapest University of Technology and Economics, Institute of Nuclear Techniques Contents
More informationDelayed Neutrons Energy Spectrum Flux Profile of Nuclear Materials in Ghana s Miniature Neutron Source Reactor Core
World Journal of Nuclear Science and Technology, 2011, 1, 26-30 doi: 10.4236/wjnst.2011.12005 Published Online July 2011 (http://www.scirp.org/journal/wjnst) Delayed Neutrons Energy Spectrum Flux Profile
More informationGUINEVERE: construction of a zero-power Pb fast ADS at Mol
GUINEVERE: construction of a zero-power Pb fast ADS at Mol A.Billebaud (CNRS/LPSC) P.Baeten, H.Aït Abderrahim, G.Ban, M.Baylac, G.Bergmans, D.Bondoux, J.Bouvier, S.Chabod, JM.De Conto, P.Dessagne, G.Gaudiot,
More informationNORArAN INTERNATIONAL PROJECT IN REACTOR PHYSICS
NORArAN INTERNATIONAL PROJECT IN REACTOR PHYSICS By Viking Olver Eriksen, Kjeller, Norway The NORA project has been in existence for about five years and one may ask what has been the experience so far
More informationEvaluation 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,
More informationPULSED NEUTRON SOURCE MEASUREMENTS OF KINETIC PARAMETERS IN THE SOURCE-DRIVEN FAST SUBCRITICAL CORE MASURCA
PULSED NEUTRON SOURCE MEASUREMENTS OF KINETIC PARAMETERS IN THE SOURCE-DRIVEN FAST SUBCRITICAL CORE MASURCA E. GONZÁLEZ-ROMERO, D. VILLAMARÍN, M. EMBID CIEMAT enrique.gonzalez@ciemat.es G. ALIBERTI, G.
More informationREACTOR PHYSICS ASPECTS OF PLUTONIUM RECYCLING IN PWRs
REACTOR PHYSICS ASPECTS OF PLUTONIUM RECYCLING IN s Present address: J.L. Kloosterman Interfaculty Reactor Institute Delft University of Technology Mekelweg 15, NL-2629 JB Delft, the Netherlands Fax: ++31
More informationMONTE 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
More informationCiclo combustibile, scorie, accelerator driven system
Ciclo combustibile, scorie, accelerator driven system M. Carta, C. Artioli ENEA Fusione e Fissione Nucleare: stato e prospettive sulle fonti energetiche nucleari per il futuro Layout of the presentation!
More informationTroitsk ADS project S.Sidorkin, E.Koptelov, L.Kravchuk, A.Rogov
Troitsk ADS project S.Sidorkin, E.Koptelov, L.Kravchuk, A.Rogov Institute for Nuclear Research RAS, Moscow, Russia Outline Linac and experimental complex Pulse neutron sources and its infrastructure Development
More informationEstimation of Control Rods Worth for WWR-S Research Reactor Using WIMS-D4 and CITATION Codes
Estimation of Control Rods Worth for WWR-S Research Reactor Using WIMS-D4 and CITATION Codes M. S. El-Nagdy 1, M. S. El-Koliel 2, D. H. Daher 1,2 )1( Department of Physics, Faculty of Science, Halwan University,
More informationWorking Party on Pu-MOX fuel physics and innovative fuel cycles (WPPR)
R&D Needs in Nuclear Science 6-8th November, 2002 OECD/NEA, Paris Working Party on Pu-MOX fuel physics and innovative fuel cycles (WPPR) Hideki Takano Japan Atomic Energy Research Institute, Japan Introduction(1)
More informationPRELIMINARY CONCEPT OF A ZERO POWER NUCLEAR REACTOR CORE
2011 International Nuclear Atlantic Conference - INAC 2011 Belo Horizonte,MG, Brazil, October 24-28, 2011 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-04-5 PRELIMINARY CONCEPT OF
More informationOECD/NEA Transient Benchmark Analysis with PARCS - THERMIX
OECD/NEA Transient Benchmark Analysis with PARCS - THERMIX Volkan Seker Thomas J. Downar OECD/NEA PBMR Workshop Paris, France June 16, 2005 Introduction Motivation of the benchmark Code-to-code comparisons.
More informationResearch Article Analysis of NEA-NSC PWR Uncontrolled Control Rod Withdrawal at Zero Power Benchmark Cases with NODAL3 Code
Hindawi Science and Technology of Nuclear Installations Volume 2017, Article ID 5151890, 8 pages https://doi.org/10.1155/2017/5151890 Research Article Analysis of NEA-NSC PWR Uncontrolled Control Rod Withdrawal
More informationStudy of Control rod worth in the TMSR
Nuclear Science and Techniques 24 (2013) 010601 Study of Control rod worth in the TMSR ZHOU Xuemei * LIU Guimin 1 Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
More informationProfile 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,
More informationTHREE-DIMENSIONAL INTEGRAL NEUTRON TRANSPORT CELL CALCULATIONS FOR THE DETERMINATION OF MEAN CELL CROSS SECTIONS
THREE-DIMENSIONAL INTEGRAL NEUTRON TRANSPORT CELL CALCULATIONS FOR THE DETERMINATION OF MEAN CELL CROSS SECTIONS Carsten Beckert 1. Introduction To calculate the neutron transport in a reactor, it is often
More informationInvestigation of Nuclear Data Accuracy for the Accelerator- Driven System with Minor Actinide Fuel
Investigation of Nuclear Data Accuracy for the Accelerator- Driven System with Minor Actinide Fuel Kenji Nishihara, Takanori Sugawara, Hiroki Iwamoto JAEA, Japan Francisco Alvarez Velarde CIEMAT, Spain
More informationUtilization 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
More information(CE~RN, G!E21ZZMA?ZOEWSPRC)
DRN PROGRAM ON LONG-LIVED WASTE TRANSMUTATION STUDIES : TRANSMUTATION POTENTIAL OF CURRENT AND INNOVATIVE SYSTEMS M. Salvatores, A. Zaetta, C. Girard, M. Delpech, I. Slessarev, J. Tommasi (CE~RN, G!E21ZZMA?ZOEWSPRC)
More informationTHORIUM SELF-SUFFICIENT FUEL CYCLE OF CANDU POWER REACTOR
International Conference Nuclear Energy for New Europe 2005 Bled, Slovenia, September 5-8, 2005 ABSTRACT THORIUM SELF-SUFFICIENT FUEL CYCLE OF CANDU POWER REACTOR Boris Bergelson, Alexander Gerasimov Institute
More informationTRANSMUTATION OF AMERICIUM AND CURIUM: REVIEW OF SOLUTIONS AND IMPACTS. Abstract
TRANSMUTATION OF AMERICIUM AND CURIUM: REVIEW OF SOLUTIONS AND IMPACTS M. Delpech, J. Tommasi, A. Zaetta DER/SPRC, CEA M. Salvatores DRN/PP, CEA H. Mouney EDF/DE G. Vambenepe EDF/SEPTEN Abstract Several
More informationEffect of Fuel Particles Size Variations on Multiplication Factor in Pebble-Bed Nuclear Reactor
International Conference Nuclear Energy for New Europe 2005 Bled, Slovenia, September 5-8, 2005 Effect of Fuel Particles Size Variations on Multiplication Factor in Pebble-Bed Nuclear Reactor Luka Snoj,
More informationTechnical Meeting on Priorities in Modeling and Simulation for Fast Neutron Systems 1
Technical Meeting on Priorities in Modeling and Simulation for Fast Neutron Systems 1 Technical Meeting on Priorities in Modeling and Simulation for Fast Neutron Systems 2 Established in 1937, Bachelor,
More informationInvariability 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
More informationAvailable online at ScienceDirect. Energy Procedia 71 (2015 )
Available online at www.sciencedirect.com ScienceDirect Energy Procedia 71 (2015 ) 97 105 The Fourth International Symposium on Innovative Nuclear Energy Systems, INES-4 High-Safety Fast Reactor Core Concepts
More informationturbine (a) (i) Which part of the power station provides thermal (heat) energy from a chain reaction?
Nuclear fission and radiation 1 The diagram shows parts of a nuclear power station. control rods boiler steam generator electricity out turbine condenser nuclear reactor (a) (i) Which part of the power
More informationCold Critical Pre-Experiment Simulations of KRUSTy
Cold Critical Pre-Experiment Simulations of KRUSTy Kristin Smith * Rene Sanchez, Ph.D. * University of Florida, Nuclear Engineering Program Los Alamos National Lab, Advanced Nuclear Technology LA-UR-17-27250
More informationA Dummy Core for V&V and Education & Training Purposes at TechnicAtome: In and Ex-Core Calculations
A Dummy Core for V&V and Education & Training Purposes at TechnicAtome: In and Ex-Core Calculations S. Nicolas, A. Noguès, L. Manifacier, L. Chabert TechnicAtome, CS 50497, 13593 Aix-en-Provence Cedex
More informationSimulating the Behaviour of the Fast Reactor JOYO
IYNC 2008 Interlaken, Switzerland, 20 26 September 2008 Paper No. 163 Simulating the Behaviour of the Fast Reactor JOYO ABSTRACT Pauli Juutilainen VTT Technical Research Centre of Finland, P.O. Box 1000,
More informationLectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 1. Title: Neutron Life Cycle
Lectures on Nuclear Power Safety Lecture No 1 Title: Neutron Life Cycle Department of Energy Technology KTH Spring 2005 Slide No 1 Outline of the Lecture Infinite Multiplication Factor, k Four Factor Formula
More informationNeutron Dose near Spent Nuclear Fuel and HAW after the 2007 ICRP Recommendations
Neutron Dose near Spent Nuclear Fuel and HAW after the 2007 ICRP Recommendations Gunter Pretzsch Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbh Radiation and Environmental Protection Division
More informationLecture 14, 8/9/2017. Nuclear Reactions and the Transmutation of Elements Nuclear Fission; Nuclear Reactors Nuclear Fusion
Lecture 14, 8/9/2017 Nuclear Reactions and the Transmutation of Elements Nuclear Fission; Nuclear Reactors Nuclear Fusion Nuclear Reactions and the Transmutation of Elements A nuclear reaction takes place
More informationBenchmark Experiment for Fast Neutron Spectrum Potassium Worth Validation in Space Power Reactor Design
Benchmark Experiment for Fast Neutron Spectrum Potassium Worth Validation in Space Power Reactor Design John D. Bess Idaho National Laboratory NETS 2015 Albuquerque, NM February 23-26, 2015 This paper
More informationSubcritical Multiplication and Reactor Startup
22.05 Reactor Physics - Part Twenty-Five Subcritical Multiplication and Reactor Startup 1. Reference Material See pp. 357-363 of the article, Light Water Reactor Control Systems, in Wiley Encyclopedia
More informationDESIGN OF B 4 C BURNABLE PARTICLES MIXED IN LEU FUEL FOR HTRS
DESIGN OF B 4 C BURNABLE PARTICLES MIXED IN LEU FUEL FOR HTRS V. Berthou, J.L. Kloosterman, H. Van Dam, T.H.J.J. Van der Hagen. Delft University of Technology Interfaculty Reactor Institute Mekelweg 5,
More informationVI. Chain Reaction. Two basic requirements must be filled in order to produce power in a reactor:
VI. Chain Reaction VI.1. Basic of Chain Reaction Two basic requirements must be filled in order to produce power in a reactor: The fission rate should be high. This rate must be continuously maintained.
More informationThe 2018 Edition of the ICSBEP Handbook
The 2018 Edition of the ICSBEP Handbook John D. Bess Margaret A. Marshall Idaho National Laboratory Tatiana Ivanova Ian Hill OECD NEA ANS 2018 Annual Meeting Philadelphia, PA 17-21 June 2018 This presentation
More informationScope and Objectives. Codes and Relevance. Topics. Which is better? Project Supervisor(s)
Development of BFBT benchmark models for sub-channel code COBRA-TF versus System Code TRACE MSc Proposal 1 Fuel Assembly Thermal-Hydraulics Comparative Assessment of COBRA-TF and TRACE for CHF Analyses
More informationNEUTRONIC ANALYSIS STUDIES OF THE SPALLATION TARGET WINDOW FOR A GAS COOLED ADS CONCEPT.
NEUTRONIC ANALYSIS STUDIES OF THE SPALLATION TARGET WINDOW FOR A GAS COOLED ADS CONCEPT. A. Abánades, A. Blanco, A. Burgos, S. Cuesta, P.T. León, J. M. Martínez-Val, M. Perlado Universidad Politecnica
More informationAnalysis of design, verification and optimization of High intensity positron source (HIPOS) at HFR Petten
Analysis of design, verification and optimization of High intensity positron source (HIPOS) at HFR Petten 1,2, K.Tuček 2, G.Daquino 2, L.Debarberis 2, A. Hogenbirk 3 1 International Atomic Energy Agency,
More informationSensitivity and Uncertainty Analysis Methodologies for Fast Reactor Physics and Design at JAEA
Sensitivity and Uncertainty Analysis Methodologies for Fast Reactor Physics and Design at JAEA Kick off meeting of NEA Expert Group on Uncertainty Analysis for Criticality Safety Assessment IRSN, France
More informationX. Neutron and Power Distribution
X. Neutron and Power Distribution X.1. Distribution of the Neutron Flux in the Reactor In order for the power generated by the fission reactions to be maintained at a constant level, the fission rate must
More informationPhysicsAndMathsTutor.com 1
PhysicsAndMathsTutor.com 1 1. Describe briefly one scattering experiment to investigate the size of the nucleus of the atom. Include a description of the properties of the incident radiation which makes
More informationChallenges in Prismatic HTR Reactor Physics
Challenges in Prismatic HTR Reactor Physics Javier Ortensi R&D Scientist - Idaho National Laboratory www.inl.gov Advanced Reactor Concepts Workshop, PHYSOR 2012 April 15, 2012 Outline HTR reactor physics
More informationAnalysis of High Enriched Uranyl Nitrate Solution Containing Cadmium
INL/CON-05-01002 PREPRINT Analysis of High Enriched Uranyl Nitrate Solution Containing Cadmium PHYSOR-2006 Topical Meeting Soon Sam Kim September 2006 This is a preprint of a paper intended for publication
More informationAdvanced Heavy Water Reactor. Amit Thakur Reactor Physics Design Division Bhabha Atomic Research Centre, INDIA
Advanced Heavy Water Reactor Amit Thakur Reactor Physics Design Division Bhabha Atomic Research Centre, INDIA Design objectives of AHWR The Advanced Heavy Water Reactor (AHWR) is a unique reactor designed
More informationThe analysis of particles of nuclear material finding the proverbial needle in a hay stack
San Diego, 18-22 February 2010 AAAS Annual Meeting 1 The analysis of particles of nuclear material finding the proverbial needle in a hay stack AAAS Annual Meeting San Diego, February 19, 2010 Klaus Luetzenkirchen
More informationChem 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
More informationProgress in Conceptual Research on Fusion Fission Hybrid Reactor for Energy (FFHR-E)
Progress in Conceptual Research on Fusion Fission Hybrid Reactor for Energy (FFHR-E) Xue-Ming Shi Xian-Jue Peng Institute of Applied Physics and Computational Mathematics(IAPCM), BeiJing, China December
More informationsustainable nuclear energy
Marcoule in service of > Atalante sustainable nuclear energy ATALANTE at the heart of international nuclear research Global energy demand will more than double in the next 40 years. Competitive, with minimal
More informationReactor-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
More informationOptimization studies of photo-neutron production in high-z metallic targets using high energy electron beam for ADS and transmutation
PRAMANA c Indian Academy of Sciences Vol. 68, No. 2 journal of February 2007 physics pp. 235 241 Optimization studies of photo-neutron production in high-z metallic targets using high energy electron beam
More informationPHYSICS A2 UNIT 2 SECTION 1: RADIOACTIVITY & NUCLEAR ENERGY
PHYSICS A2 UNIT 2 SECTION 1: RADIOACTIVITY & NUCLEAR ENERGY THE ATOMIC NUCLEUS / NUCLEAR RADIUS & DENSITY / PROPERTIES OF NUCLEAR RADIATION / INTENSITY & BACKGROUND RADIATION / EXPONENTIAL LAW OF DECAY
More informationChain Reactions. Table of Contents. List of Figures
Chain Reactions 1 Chain Reactions prepared by Wm. J. Garland, Professor, Department of Engineering Physics, McMaster University, Hamilton, Ontario, Canada More about this document Summary: In the chapter
More informationA new method to acquire nuclear fission data using heavy ion reactions a way to understand the fission phenomenon
press release date Friday 26 August 15:00 (material distribution) Education, Culture, Sports, Science Press conf., Nuclear Regulatory Agency Press conf., Ibaraki Pref.. Government press conf., Osaka Science
More informationStudy of the End Flux Peaking for the CANDU Fuel Bundle Types by Transport Methods
International Conference Nuclear Energy for New Europe 2005 Bled, Slovenia, September 5-8, 2005 Study of the End Flux Peaking for the CANDU Fuel Bundle Types by Transport Methods ABSTRACT Victoria Balaceanu,
More informationNUCLEAR 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
More informationReport of Workshop on EXFOR Compilation 2014
Report of Workshop on EXFOR Compilation 2014 DAGVADORJ Ichinkhorloo Meme Media Laboratory, Hokkaido University Abstract The Workshop on The Experimental Nuclear Reaction Data Database compilation was held
More informationProgress in Conceptual Research on Fusion Fission Hybrid Reactor for Energy
Progress in Conceptual Research on Fusion Fission Hybrid Reactor for Energy Xueming Shi 1, Xi Wang, Xianjue Peng 1) Institute of Applied Physics and Computational Mathematics Corresponding author: sxm_shi@iapcm.ac.cn
More informationASSESSMENT OF THE EQUILIBRIUM STATE IN REACTOR-BASED PLUTONIUM OR TRANSURANICS MULTI-RECYCLING
ASSESSMENT OF THE EQUILIBRIUM STATE IN REACTOR-BASED PLUTONIUM OR TRANSURANICS MULTI-RECYCLING T.K. Kim, T.A. Taiwo, J.A. Stillman, R.N. Hill and P.J. Finck Argonne National Laboratory, U.S. Abstract An
More informationNeutron Multiplicity Measurements for the AFCI Program
Neutron Multiplicity Measurements for the AFCI Program Purpose and Problem Statement Quarterly Progress Report June-August 2004 UNLV Transmutation Research Project Principle Investigator: Denis Beller,
More information