PWR AND WWER MOX BENCHMARK CALCULATION BY HELIOS
|
|
- Gavin Wilkerson
- 5 years ago
- Views:
Transcription
1 PWR AND WWER MOX BENCHMARK CALCULATION BY HELIOS Radoslav ZAJAC 1,2), Petr DARILEK 1), Vladimir NECAS 2) 1 VUJE, Inc., Okruzna 5, Trnava, Slovakia; zajacr@vuje.sk, darilek@vuje.sk 2 Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Ilkovicova 3, Bratislava, Slovakia; vladimir.necas@stuba.sk ABSTRACT A depletion calculation benchmark devoted to MOX fuel cycles in an ongoing objective of OECD/NEA WPRS (Working Party on Scientific Issues of Reactor Systems) following the study of depletion calculation concerning UOX fuel [1]. Four corresponding fuel structures as super-cells were calculated: the MOX PWR, WWER-1000, WWER-440 assembly surrounded by UOX assembly and MOX assembly in an infinite lattice. These scenarios enable to show the importance of the UOX environment in the mixed UOX - MOX core. Studies have shown that a standard calculation based on an infinite medium pattern for MOX assembly can lead to a significant error in Pu-239 concentration at a high burn up. The model calculations were performed by a spectral code HELIOS INTRODUCTION The MOX is a means to re-use plutonium remaining in spent reactor fuel to provide electricity generation [2]. The MOX production demands plutonium and the remaining uranium separation (about 97 % of the spent fuel) from the fission products (FPs) (together about 3 %). Then plutonium needs to be separated from most or all of the uranium. All this is undertaken at a reprocessing plant. Plutonium as an oxide is mixed with depleted uranium left over from an enrichment plant to form fresh mixed oxide fuel (MOX = UO 2 + PuO 2 ). The MOX fuel, consisting of about 7-9 % Pu mixed with depleted U, is equivalent to UOX fuel enriched to about 4.5 % U-235 assuming that Pu has about two thirds of fissile isotopes [2]. When uranium prices were low the reprocessing to separate Pu for recycling at MOX was not itself economic. But with the rise of natural uranium prices coupled with reducing the spent fuel volume is becoming so [2] [3].
2 2. MODEL SPECIFICATIONS OF THE CALCULATIONS In this paper are presented six calculated models of the MOX assembly (fig 1-6). The first three models (fig 1-3) typify MOX assembly in the case of a mixed core. The mixed core is loaded by 30 % of the recycled Pu. The MOX assembly of three different rector types (PWR 900 MWe, WWER-1000 and WWER-440) on the figures 1, 2 and 3 is surrounded by UOX assemblies. The next three cases (fig 4-6) represent the MOX assembly of PWR 900, WWER-1000 and WWER-440 reactor in the infinite lattice. The standard MOX assembly used in this study includes three zones with different Pu contents to flatten the within assembly power distribution and to attenuate fission rate discontinuities at the MOX-UOX interface. The central zone is characterised by a high Pu content (5.5 %) and a peripheral zone by a low Pu content (2.85 %). The MOX PWR assembly profiling was used from the depletion calculation benchmark devoted to MOX fuel cycles in an ongoing objective of OECD/NEA WPRS (Working Party on Scientific Issues of Reactor Systems) [1]. This benchmark is directly connected with the French Post Irradiation Examination (PIE) program [4]. The profiling of MOX WWER-1000 and WWER-440 assembly was adopted from the MOX PWR assembly and the Pu content in each zone is the same as in the PWR MOX fuel assembly. All kinds of calculations were performed by the spectral computer code HELIOS SUPERCELL MODELS The requested calculations were performed to attain a constant target burn up of 42 GWd/tHM for all of the studied MOX fuel assemblies. The following figures (fig.1, 2 and 3) of MOX assembly surrounded by UOX assemblies - super cells is shown. The first super cell (fig. 1) consists of eight UOX PWR assemblies and the MOX PWR fuel assembly is situated in the centre of the super cell. The fig. 2 shows the super cell of WWER Six WWER-1000 UOX assemblies surround the central WWER-1000 MOX assembly. A design of the fig. 3 is very similar to fig.2. The MOX WWER-440 fuel assembly in the centre with six UOX WWER-440 fuel assemblies is demonstrated. Each one of all the super cell models is calculated by periodic boundary conditions. The three following operating periods of fuel cycle represent the MOX fuel irradiation history [1]: 1 st period: 285 full power days, burn up = 12 GWd/tHM Down time: 60 days 2 nd period: 300 full power days, burn up = 25 GWd/tHM Down time: 40 days 3 rd period: 280 full power days, burn up = 42 GWd/tHM
3 MOX PWR Assembly UOX PWR Assembly Fig. 1: MOX-UOX PWR geometry. Pu/(U+Pu+Am) = 4.42 % Burn up of UOX assembly: (24 GWd/tHM + 34 GWd/tHM) final 58 GWd/tHM Burn up of MOX assembly: app. 42 GWd/tHM Red - high (5.516 % Pu) Blue - medium (4.334 % Pu) Pink - low (2.856 % Pu) MOX WWER-1000 Assembly UOX WWER-1000 Assembly Fig. 2: Position of the MOX WWER-1000 in WWER-1000 supercell. Pu/(U+Pu+Am) = 4.42 % Burn up of UOX assembly: (24 GWd/tHM + 31 GWd/tHM) final 55 GWd/tHM Burn up of MOX assembly: app. 42 GWd/tHM Red - high (5.516 % Pu) Blue - medium (4.334 % Pu) Pink - low (2.856 % Pu)
4 MOX WWER-440 Assembly UOX WWER-440 Assembly Pu/(U+Pu+Am) = 4.42 % Geometry: Gd-2 assembly Burn up of UOX assembly: (24 GWd/tHM + 31 GWd/tHM) final 55 GWd/tHM Burn up of MOX assembly: app. 42 GWd/tHM Red - high (5.516 % Pu) Blue - medium (4.334 % Pu) Pink - low (2.856 % Pu) Fig. 3: MOX - UOX WWER-440 geometry. 2.2 MOX FUEL ASSEMBLIES, INFINITE LATTICE The profiled MOX fuel assemblies of the PWR 900, WWER-1000 and WWER-440 are shown on fig. 4, 5 and 6. Boundary conditions were set in HELIOS 1.10 for infinite lattice calculation for all of the studied assemblies. The final burn up was proposed to the same value as in super cell - 42 GWd/tHM. Fig. 4: MOX PWR assembly. Fig. 5: MOX WWER-1000 assembly. Fig. 6: MOX WWER-440 assembly.
5 2.3 MOX FUEL COMPOSITIONS The listed initial MOX composition is a representative of the realistic UOX fuel irradiated in a mixed MOX - UOX LWR core [1]. This MOX fuel consists of a typical plutonium vector for material derivated from reprocessing of thermal reactor UOX fuel. Plutonium isotopic composition, corresponding to the three Pu content zones, is given in Tab. 1 and uranium isotopic composition in Tab. 2. Tab.1: Plutonium isotopic composition in fresh MOX fuel [1]. Nuclide Isotopic Composition [Atom.%] Pu Pu Pu Pu Pu Am Tab.2: Uranium isotopic composition in fresh MOX fuel [1]. Nuclide Isotopic Composition [Atom.%] U U U U Tab.3: Initial MOX fuel content [1]. Pu content in the zone Plutonium Content, w/o Pu(total) + Am/[U+Pu+Am] High 5.6 Medium 4.4 Low 2.9 Plutonium from reprocessed fuel is usually fabricated into the MOX fuel as soon as possible to avoid problems with the decay of short-lived Pu isotopes [2]. In particular, Pu-241 (halflive years [5]) decays to Am-241 which is a strong gamma emitter, giving rise to a potential occupational health hazard. It is so if separated Pu, over five years old, is used in a normal MOX plant. The Am-241 level in stored Pu increases about 0.5 % per year with corresponding decrease in fissile value of the Pu [2]. Content of Pu-238 (half-live 87.7 years [5]) is increased in high-burn up fuel. It is a strong alpha emitter and a source of spontaneous neutrons. Pu-239, Pu-240 and Pu-242 are long-lived and hence little changed with prolonged storage [2]. 2.4 UOX FUEL COMPOSITIONS For the calculations, the adjacent UOX fuel assemblies are modeled as already burned. They have an initial enrichment of 3.25 w/o and have reached a burn up of 24 GWd/tHM [1].
6 3. RESULTS AND CONCLUSIONS The Pu weight concentrations at MOX PWR assembly as a super cell part and as a part of infinite lattice are listed in tab. 4. The weight concentration final values in Pu high and Pu medium zones are similar but the values in the Pu low zone are different. These differences are caused by the fission rate discontinuities at the MOX-UOX interface. The Pu development in the zones of MOX PWR assembly as a part of structure depending on burn up is shown on the fig. 7. In all of the zones the Pu content decreases with burn up value. The comparison of average weight concentrations for MOX PWR, WWER-1000 and WWER-400 assembly in the infinite lattice and as a part of the super cell are presented in tab.5. The Pu-239, Pu-242, Pu and MA development of MOX PWR, WWER-1000 and WWER-440 assembly in the infinite lattice is presented on the last figure (fig. 8). The Pu content decreases in all of the Pu cases. MA dependance on the burn up slowly rises. On the base of results it is possible to see a Pu reduction in all of calculated cases. The reductions between initial and final burn up values for MOX assembly as a part of super cell: Pu-239 (PWR): -63 % Pu-239 (WWER-1000): -62 % Pu-239 (WWER-440): -54 % Pu (PWR): -33 % Pu (WWER-1000): -32 % Pu (WWER-440): -27 % Spent LWR UOX fuel containes of approximately 1 % of Pu. Then 4.5 LWR UOX assemblies are neccesary to reprocess for production of 1 MOX assembly with 4.42 % Pu content. If it is possible to spent 60 % of Pu-239 in MOX fuel then this Pu-239 depletion leads to Pu-239 spending from 2.7 LWR UOX assemblies. REFERENCES [1] ROQUE, B. MARIMBEAU, P. GROUILLER, J.P.: Specification for the Phase 2 of a Depletion Calculation Benchmark devoted to MOX Fuel Cycles. WPRS NEA/OECD. December [2] World Nuclear Association, Mixed Oxide (MOX) Fuel, online, [3] SEBIAN, V.: Transmutation of radionuclides of spent fuel in WWER-440 reactors, (PhD thesis). Slovak University of Technology, March [4] ROQUE, B. MARIMBEAU, P. BIOUX, P.:The French Post Irradiation Examination Database for the validation of depletion calculation tools, Post Irradiation Examination (PIE) program, [5] TULI, K. J.: Nuclear Wallet Cards, National Nuclear Data Center, April [6] BAILLY, H. MENESSIER, D. PRUNIER, C.: The Nuclear Fuel of Pressurized Water Reactors and Fast Reactors. Lavoisier Publishing, [7] Manual: Helios 1.10, [8] Darilek, P.,Zajac,R.,Breza,J.,Necas,V.:Comparison of PWR-IMF and FR fuel cycles. In: 2007 GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems,pp
7 Tab. 4: Weight concenrations [%] in the zones of MOX PWR assembly as super cell part. PWR Nuclide Initial [%], MOX Assembly in Super Cell, 42 GWd/tHM MOX Assembly in Infinite lattice, 42 GWd/tHM 0 GWd/tHM High [%] Medium [%] Low [%] Average [%] High [%] Medium [%] Low [%] Average [%] U Np Np Pu Pu Pu Pu Pu Am Pu Total MA Total Tab. 5: Average weight concentrations [%] in MOX assembly of PWR-900, WWER-1000 and WWER-440 reactor. Reactor Nuclide Initial [%], PWR-900, 42 GWd/tHM WWER-1000, 42 GWd/tHM WWER-440, 42 GWd/tHM 0 GWd/tHM Super Cell [%] Infinite L. [%] Super Cell [%] Infinite L. [%] Super Cell [%] Infinite L. [%] U Np Np Pu Pu Pu Pu Pu Am Pu Total MA Total
8 Pu-239 (HIGH) (Np+Am+Cm+Bk+Cf) HIGH (Np+Am+Cm+Bk+Cf) MEDIUM Pu(MOX PWR) LOW Pu-239 (MEDIUM) Pu(MOX PWR) HIGH Pu(MOX PWR) MEDIUM Pu-239 (LOW) (Np+Am+Cm+Bk+Cf) LOW 4.0 [%] GWd/tHM (super cell) Fig. 7: Development of Pu in the zones of MOX PWR assembly as a super cell part Pu-239 (PWR) Pu(MOX PWR) Pu-239 (WWER1000) Pu(MOX WWER1000) Pu-239 (WWER440) Pu(MOX WWER440) Pu-242 (PWR) (Np+Am+Cm+Bk+Cf) PWR Pu-242 (WWER1000) (Np+Am+Cm+Bk+Cf) WWER1000 Pu-242 (WWER440) (Np+Am+Cm+Bk+Cf) WWER [%] GWd/tHM (assembly) Fig. 8: Development of Pu in the MOX PWR, WWER-1000 and WWER-440 assembly in the infinite lattice.
THE INTEGRATION OF FAST REACTOR TO THE FUEL CYCLE IN SLOVAKIA
THE INTEGRATION OF FAST REACTOR TO THE FUEL CYCLE IN SLOVAKIA Radoslav ZAJAC, Petr DARILEK VUJE, Inc. Okruzna 5, SK-91864 Trnava, Slovakia Tel: +421 33 599 1316, Fax: +421 33 599 1191, Email: zajacr@vuje.sk,
More informationEnglish text only NUCLEAR ENERGY AGENCY NUCLEAR SCIENCE COMMITTEE
Unclassified NEA/NSC/DOC(2007)9 NEA/NSC/DOC(2007)9 Unclassified Organisation de Coopération et de Développement Economiques Organisation for Economic Co-operation and Development 14-Dec-2007 English text
More informationMOx Benchmark Calculations by Deterministic and Monte Carlo Codes
MOx Benchmark Calculations by Deterministic and Monte Carlo Codes G.Kotev, M. Pecchia C. Parisi, F. D Auria San Piero a Grado Nuclear Research Group (GRNSPG), University of Pisa via Diotisalvi 2, 56122
More informationNuclear Data for Reactor Physics: Cross Sections and Level Densities in in the Actinide Region. J.N. Wilson Institut de Physique Nucléaire, Orsay
Nuclear Data for Reactor Physics: Cross Sections and Level Densities in in the Actinide Region J.N. Wilson Institut de Physique Nucléaire, Orsay Talk Plan Talk Plan The importance of innovative nuclear
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 informationIAEA-TECDOC Nuclear Fuel Cycle Simulation System (VISTA)
IAEA-TECDOC-1535 Nuclear Fuel Cycle Simulation System (VISTA) February 2007 IAEA-TECDOC-1535 Nuclear Fuel Cycle Simulation System (VISTA) February 2007 The originating Section of this publication in the
More informationPrototypes and fuel cycle options including transmutation
A S T R I D Prototypes and fuel cycle options including transmutation General introduction, GEN IV fast reactors Transmutation demonstration Fuel cycle Conclusions www.cea.fr DEN/CAD/DER/CPA Jean-Paul
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 informationTechnical workshop : Dynamic nuclear fuel cycle
Technical workshop : Dynamic nuclear fuel cycle Reactor description in CLASS Baptiste LENIAU* Institut d Astrophysique de Paris 6-8 July, 2016 Introduction Summary Summary The CLASS package : a brief overview
More informationQuestion to the class: What are the pros, cons, and uncertainties of using nuclear power?
Energy and Society Week 11 Section Handout Section Outline: 1. Rough sketch of nuclear power (15 minutes) 2. Radioactive decay (10 minutes) 3. Nuclear practice problems or a discussion of the appropriate
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 informationMULTI-RECYCLING OF TRANSURANIC ELEMENTS IN A MODIFIED PWR FUEL ASSEMBLY. A Thesis ALEX CARL CHAMBERS
MULTI-RECYCLING OF TRANSURANIC ELEMENTS IN A MODIFIED PWR FUEL ASSEMBLY A Thesis by ALEX CARL CHAMBERS Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the
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 informationThe Effect of Burnup on Reactivity for VVER-1000 with MOXGD and UGD Fuel Assemblies Using MCNPX Code
Journal of Nuclear and Particle Physics 2016, 6(3): 61-71 DOI: 10.5923/j.jnpp.20160603.03 The Effect of Burnup on Reactivity for VVER-1000 with MOXGD and UGD Fuel Assemblies Using MCNPX Code Heba K. Louis
More informationScience and Technology. Solutions, Separation Techniques, and the PUREX Process for Reprocessing Nuclear Waste
Science and Technology Solutions, Separation Techniques, and the PUREX Process for Reprocessing Nuclear Waste Spent Fuel Rods General Accounting Office Fission products that emit beta and gamma radiation
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 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 informationProduction. David Nusbaum Project on Managing the Atom, Belfer Center October 4, 2011
Production David Nusbaum Project on Managing the Atom, Belfer Center October 4, 2011 Where are we? Nuclear Fuel Cycle Background Pu- Radioactive, chemical element, of the actinoid series of the periodic
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 informationParametric Studies of the Effect of MOx Environment and Control Rods for PWR-UOx Burnup Credit Implementation
42 Parametric Studies of the Effect of MOx Environment and Control Rods for PWR-UOx Burnup Credit Implementation Anne BARREAU 1*, Bénédicte ROQUE 1, Pierre MARIMBEAU 1, Christophe VENARD 1 Philippe BIOUX
More informationImprovements of Isotopic Ratios Prediction through Takahama-3 Chemical Assays with the JEFF3.0 Nuclear Data Library
PHYSOR 2004 -The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments Chicago, Illinois, April 25-29, 2004, on CD-ROM, American Nuclear Society, Lagrange Park, IL. (2004) Improvements
More informationCriticality analysis of ALLEGRO Fuel Assemblies Configurations
Criticality analysis of ALLEGRO Fuel Assemblies Configurations Radoslav ZAJAC Vladimír CHRAPČIAK 13-16 October 2015 5th International Serpent User Group Meeting at Knoxville, Tennessee ALLEGRO Core - Fuel
More informationPresent Status of JEFF-3.1 Qualification for LWR. Reactivity and Fuel Inventory Prediction
Present Status of JEFF-3.1 Qualification for LWR Reactivity and Fuel Inventory Prediction Experimental Validation Group (CEA Cadarache/Saclay) D. BERNARD david.bernard@cea.fr A. COURCELLE arnaud.courcelle@cea.fr
More informationNuclear Fuel Cycle and WebKOrigen
10th Nuclear Science Training Course with NUCLEONICA Institute of Nuclear Science of Ege University, Cesme, Izmir, Turkey, 8th-10th October 2008 Nuclear Fuel Cycle and WebKOrigen Jean Galy European Commission
More informationIncineration of Plutonium in PWR Using Hydride Fuel
Incineration of Plutonium in PWR Using Hydride Fuel Francesco Ganda and Ehud Greenspan University of California, Berkeley ARWIF-2005 Oak-Ridge, TN February 16-18, 2005 Pu transmutation overview Many approaches
More informationVALMOX VALIDATION OF NUCLEAR DATA FOR HIGH BURNUP MOX FUELS
VALMOX VALIDATION OF NUCLEAR DATA FOR HIGH BURNUP MOX FUELS B. Lance, S. Pilate (Belgonucléaire Brussels), R. Jacqmin, A. Santamarina (CEA Cadarache), B. Verboomen (SCK-CEN Mol), J.C. Kuijper (NRG Petten)
More informationRecycling Spent Nuclear Fuel Option for Nuclear Sustainability and more proliferation resistance In FBR
Recycling Spent Nuclear Fuel Option for Nuclear Sustainability and more proliferation resistance In FBR SIDIK PERMANA a, DWI IRWANTO a, MITSUTOSHI SUZUKI b, MASAKI SAITO c, ZAKI SUUD a a Nuclear Physics
More informationTarget accuracy of MA nuclear data and progress in validation by post irradiation experiments with the fast reactor JOYO
Target accuracy of MA nuclear data and progress in validation by post irradiation experiments with the fast reactor JOYO Shigeo OHKI, Kenji YOKOYAMA, Kazuyuki NUMATA *, and Tomoyuki JIN * Oarai Engineering
More informationProliferation-Proof Uranium/Plutonium Fuel Cycles Safeguards and Non-Proliferation
Proliferation-Proof Uranium/Plutonium Fuel Cycles Safeguards and Non-Proliferation SUB Hamburg by Gunther KeBler A 2012/7138 Scientific Publishing id- Contents 1 Nuclear Proliferation and IAEA-Safeguards
More informationRadioactive Inventory at the Fukushima NPP
Radioactive Inventory at the Fukushima NPP G. Pretzsch, V. Hannstein, M. Wehrfritz (GRS) Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbh Schwertnergasse 1, 50667 Köln, Germany Abstract: The paper
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 informationDecay heat calculations. A study of their validation and accuracy.
Decay heat calculations A study of their validation and accuracy. Presented by : Dr. Robert W. Mills, UK National Nuclear Laboratory. Date: 01/10/09 The UK National Nuclear Laboratory The NNL (www.nnl.co.uk)
More informationREVIEW OF RESULTS FOR THE OECD/NEA PHASE VII BENCHMARK: STUDY OF SPENT FUEL COMPOSITIONS FOR LONG-TERM DISPOSAL
REVIEW OF RESULTS FOR THE OECD/NEA PHASE VII BENCHMARK: STUDY OF SPENT FUEL COMPOSITIONS FOR LONG-TERM DISPOSAL Georgeta Radulescu John Wagner (presenter) Oak Ridge National Laboratory International Workshop
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 informationMA/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,
More informationIAEA-TECDOC-1349 Potential of thorium based fuel cycles to constrain plutonium and reduce long lived waste toxicity
IAEA-TECDOC-1349 Potential of thorium based fuel cycles to constrain plutonium and reduce long lived waste toxicity Final report of a co-ordinated research project 1995 2001 April 2003 The originating
More informationUse of Burn-Up Credit in the Assessment of Criticality Risk
Use of Burn-Up Credit in the Assessment of Criticality Risk Date: 31 st August 2017 Author(s): D Hanlon, S Richards, T Ware, B Lindley, J Porter & M Brady Raap Client Reference: Amec Foster Wheeler Reference:
More informationDevelopment of depletion models for radionuclide inventory, decay heat and source term estimation in discharged fuel
Development of depletion models for radionuclide inventory, decay heat and source term estimation in discharged fuel S. Caruso, A. Shama, M. M. Gutierrez National Cooperative for the Disposal of Radioactive
More informationCriticality Safety in the Waste Management of Spent Fuel from NPPs
Criticality Safety in the Waste Management of Spent Fuel from NPPs Robert Kilger (GRS) Garching / Forschungszentrum, Boltzmannstr. 14, D-85748 Garching n. Munich Abstract: During irradiation in the reactor
More informationTechnical note on using JEFF-3.1 and JEFF data to calculate neutron emission from spontaneous fission and (α,n) reactions with FISPIN.
Page 1 of 11 Technical note on using JEFF-3.1 and JEFF-3.1.1 data to calculate neutron emission from spontaneous fission and (α,n) reactions with FISPIN. Nexia Solutions Ltd Dr. Robert W. Mills and Dr.
More informationPEBBLE BED REACTORS FOR ONCE THROUGH NUCLEAR TRANSMUTATION.
PEBBLE BED REACTORS FOR ONCE THROUGH NUCLEAR TRANSMUTATION. Pablo León, José Martínez-Val, Alberto Abánades and David Saphier. Universidad Politécnica de Madrid, Spain. C/ J. Gutierrez Abascal Nº2, 28006
More informationSPentfuel characterisation Program for the Implementation of Repositories
SPentfuel characterisation Program for the Implementation of Repositories WP2 & WP4 Development of measurement methods and techniques to characterise spent nuclear fuel Henrik Widestrand and Peter Schillebeeckx
More informationStudy of Burnup Reactivity and Isotopic Inventories in REBUS Program
Study of Burnup Reactivity and Isotopic Inventories in REBUS Program T. Yamamoto 1, Y. Ando 1, K. Sakurada 2, Y. Hayashi 2, and K. Azekura 3 1 Japan Nuclear Energy Safety Organization (JNES) 2 Toshiba
More informationTRANSMUTATION OF LONG-LIVED NUCLIDES IN THE FUEL CYCLE OF BREST-TYPE REACTORS. A.V. Lopatkin, V.V. Orlov, A.I. Filin (RDIPE, Moscow, Russia)
TRANSMUTATION OF LONG-LIVE NUCLIES IN THE FUEL CYCLE OF BREST-TYPE REACTORS A.V. Lopatkin, V.V. Orlov, A.I. Filin RIPE, Moscow, Russia) 947 1. Background Radiation background is an integral part of nature
More informationActivation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB
Activation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB K. M. Feng (Southwestern Institute of Physics, China) Presented at 8th IAEA Technical Meeting on Fusion Power Plant Safety
More informationKYT2018 TECHNOLOGIES IN NUCLEAR WASTE MANAGEMENT
KYT2018 TECHNOLOGIES IN NUCLEAR WASTE MANAGEMENT KYT2018 midterm seminar, April 7 th, 2017 Finlandia Hall, Helsinki RESEARCH CONTINUATION KYT2018 Technologies in nuclear waste management Advanced fuel
More informationThere are no stable isotopes of elements above atomic number 83.
Nuclear Chemistry Stability of isotopes is based on the ratio of neutrons and protons in its nucleus. Although most nuclei are stable, some are unstable and spontaneously decay, emitting radiation. All
More informationAnalysis of Multi-recycle Thorium Fuel Cycles in Comparison with Oncethrough
Analysis of Multi-recycle Thorium Fuel Cycles in Comparison with Oncethrough Fuel Cycles A Thesis Presented to The Academic Faculty by Lloyd Michael Huang In Partial Fulfillment of the Requirements for
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 informationESTIMATION OF MAXIMUM PERMISSIBLE STEP LOSSES IN P&T PROCESSING
ESTIMATION OF MAXIMUM PERMISSIBLE STEP LOSSES IN P&T PROCESSING Jan-Olov Liljenzin Nuclear Chemistry, Department of Chemical and Biological Engineering Chalmers University of Technology, Gothenburg, Sweden
More informationSpent fuel inventory calculations in the SPIRE project: Current limits and expected improvements
WIR SCHAFFEN WISSEN HEUTE FÜR MORGEN D. Rochman and M. Seidl, for the SPIRE project Spent fuel inventory calculations in the SPIRE project: Current limits and expected improvements Implementing Geological
More informationRequests on Nuclear Data in the Backend Field through PIE Analysis
Requests on Nuclear Data in the Backend Field through PIE Analysis Yoshihira Ando 1), Yasushi Ohkawachi 2) 1) TOSHIBA Corporation Power System & Services Company Power & Industrial Systems Research & Development
More informationParametric Study of Control Rod Exposure for PWR Burnup Credit Criticality Safety Analyses
35281 NCSD Conference Paper #2 7/17/01 3:58:06 PM Computational Physics and Engineering Division (10) Parametric Study of Control Rod Exposure for PWR Burnup Credit Criticality Safety Analyses Charlotta
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 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 informationIndicators for quantifying proliferation risk and nuclear waste issues in energy system models
??? s t or aget i me Indicators for quantifying proliferation risk and nuclear waste issues in energy system models Master s Thesis in Engineering Physics HENRIK WALL Department of Energy and Environment
More informationNuclear Data for Emergency Preparedness of Nuclear Power Plants Evaluation of Radioactivity Inventory in PWR using JENDL 3.3
Nuclear Data for Emergency Preparedness of Nuclear Power Plants Evaluation of Radioactivity Inventory in PWR using JENDL 3.3 Yoshitaka Yoshida, Itsuro Kimura Institute of Nuclear Technology, Institute
More informationSome thoughts on Fission Yield Data in Estimating Reactor Core Radionuclide Activities (for anti-neutrino estimation)
Some thoughts on Fission Yield Data in Estimating Reactor Core Radionuclide Activities (for anti-neutrino estimation) Dr Robert W. Mills, NNL Research Fellow for Nuclear Data, UK National Nuclear Laboratory.
More informationCore Physics Second Part How We Calculate LWRs
Core Physics Second Part How We Calculate LWRs Dr. E. E. Pilat MIT NSED CANES Center for Advanced Nuclear Energy Systems Method of Attack Important nuclides Course of calc Point calc(pd + N) ϕ dn/dt N
More informationНациональный исследовательский Томский политехнический университет
ЯДЕРНО ТОПЛИВНЫЙ ЦИКЛ Зяблова Н.Н, Карпова Н.Д. Национальный исследовательский Томский политехнический университет Томск, Россия Данная статья раскрывает понятие ядерно топливного цикла. Объясняет его
More informationCommunication 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
More informationImpact of Photon Transport on Power Distribution
Impact of Photon Transport on Power Distribution LIEGEARD Clément, CALLOO Ansar, MARLEAU Guy, GIRARDI Enrico Électricité de France, R&D, Simulation neutronique techniques de l information et calcul scientifique
More informationSMOPY a new NDA tool for safeguards of LEU and MOX spent fuel
SMOPY a new NDA tool for safeguards of LEU and MOX spent fuel IAEA-SM-367/14/03 A. LEBRUN, French Atomic Energy Commission, CEA Cadarache 13115 St. Paul Lez Durance M. MERELLI, J-L. SZABO, French Atomic
More information(1) SCK CEN, Boeretang 200, B-2400 Mol, Belgium (2) Belgonucléaire, Av. Arianelaan 4, B-1200 Brussels, Belgium
The REBUS Experimental Programme for Burn-up Credit Peter Baeten (1)*, Pierre D'hondt (1), Leo Sannen (1), Daniel Marloye (2), Benoit Lance (2), Alfred Renard (2), Jacques Basselier (2) (1) SCK CEN, Boeretang
More informationRadiotoxicity Characterization of Multi-Recycled Thorium Fuel
Radiotoxicity Characterization of Multi-Recycled Thorium Fuel - 12394 F. Franceschini 1, C. Fiorina 2,4, M. Huang 3, B. Petrovic 3, M. Wenner 1, J. Krepel 4 1 Westinghouse Electric Company, Cranberry Township,
More informationNucleonica Lab. Case Study: Characterisation of an irradiated fuel sample (UOX) from a PWR. Dr. Joseph Magill, Nucleonica GmbH, Karlsruhe
A 1.5 h course to be held at the JRC Ispra at the 5th International Summer School 2013: Operational Issues in Radioactive Waste Management and Nuclear Decommissioning Nucleonica Lab Case Study: Characterisation
More informationLow-Grade Nuclear Materials as Possible Threats to the Nonproliferation Regime. (Report under CRDF Project RX0-1333)
Low-Grade Nuclear Materials as Possible Threats to the Nonproliferation Regime (Report under CRDF Project RX0-1333) 2 Abstract This study addresses a number of issues related to low-grade fissile materials
More informationNuclear Data Uncertainty Quantification for Applications in Energy, Security, and Isotope Production
Nuclear Data Uncertainty Quantification for Applications in Energy, Security, and Isotope Production I. Gauld M. Williams M. Pigni L. Leal Oak Ridge National Laboratory Reactor and Nuclear Systems Division
More informationReduction of Radioactive Waste by Accelerators
October 9-10, 2014 International Symposium on Present Status and Future Perspective for Reducing Radioactive Waste - Aiming for Zero-Release - Reduction of Radioactive Waste by Accelerators Hiroyuki Oigawa
More informationmore ?Learning about plutonium
?Learning about plutonium more What is plutonium? Plutonium (PU) is a hard white metal that looks like iron. It melts at 640 Celsius, turns into plutonium oxide when exposed to air and can catch fire.
More informationCarbon Dating. Principles of Radiometric Dating. 03 nuclear decay and the standard model June 05, 2013
Principles of Radiometric Dating http://facstaff.gpc.edu/~pgore/geology/geo102/radio.htm Naturally occurring radioactive materials break down into other materials at known rates. This is known as radioactive
More informationTransmutation: reducing the storage time of spent fuel
Open Access Journal Journal of Power Technologies 94 (Nuclear Issue) (2014) 27 34 journal homepage:papers.itc.pw.edu.pl Transmutation: reducing the storage time of spent fuel Piotr Mazgaj, Piotr Darnowski
More informationStudy on Nuclear Transmutation of Nuclear Waste by 14 MeV Neutrons )
Study on Nuclear Transmutation of Nuclear Waste by 14 MeV Neutrons ) Takanori KITADA, Atsuki UMEMURA and Kohei TAKAHASHI Osaka University, Graduate School of Engineering, Division of Sustainable Energy
More informationREACTOR PHYSICS CALCULATIONS ON MOX FUEL IN BOILING WATER REACTORS (BWRs)
REACTOR PHYSICS CALCULATIONS ON MOX FUEL IN BOILING ATER REACTORS (BRs) Christophe Demazière Chalmers University of Technology Department of Reactor Physics SE-42 96 Gothenburg Sweden Abstract The loading
More informationThe outermost container into which vitrified high level waste or spent fuel rods are to be placed. Made of stainless steel or inert alloy.
Glossary of Nuclear Waste Terms Atom The basic component of all matter; it is the smallest part of an element having all the chemical properties of that element. Atoms are made up of protons and neutrons
More information7 th International Summer School 2015, JRC Ispra: Operational Issues in Radioactive Waste Management and Nuclear Decommissioning
7 th International Summer School 2015, JRC Ispra: Operational Issues in Radioactive Waste Management and Nuclear Decommissioning Nucleonica: Nuclear Applications for Radioactive Waste Management and Decommissioning
More informationNew Developments in Actinides Burning with Symbiotic LWR- HTR-GCFR Fuel Cycles
IYNC 2008 Interlaken, Switzerland, 20 26 September 2008 Paper No. XYZ New Developments in Actinides Burning with Symbiotic LWR- HTR-GCFR Fuel Cycles Eleonora Bomboni 1 1 Department of Mechanical, Nuclear
More informationPLUTONIUM RECYCLING IN PRESSURIZED WATER REACTORS: INFLUENCE OF THE MODERATOR-TO-FUEL RATIO
PLUTONIUM RECYCLING IN PRESSURIZED WATER REACTORS: INFLUENCE OF THE MODERATOR-TO-FUEL RATIO FISSION REACTORS KEYWORDS: plutonium recycling, moderator-to-fuel ratio, PWR JAN LEEN KLOOSTERMAN* Delft University
More informationRadiochemistry in reactor
Radiochemistry in reactor Readings: Radiochemistry in Light Water Reactors, Chapter 3 Speciation in irradiated fuel Utilization of resulting isotopics Fission Product Chemistry Fuel confined in reactor
More informationnuclear chemical change CH4 + 2O2 CO2 + 2H2O carbon dating
Nuclear Chemistry I. What is nuclear chemistry? a. Nuclear changes vs. chemical changes i. A nuclear change is a change in which the nucleons (things in the nucleus) change. For instance, if the number
More informationNuclear Theory - Course 127 FISSION
Nuclear Theory - Course 127 FISSION After having looked at neutron reactions in general, we shall use this lesson to describe the fission reaction and its products in some detail. The Fission Reaction
More informationEffect of Axial Burnup on Power Distribution and Isotope Inventory for a PWR Fuel Assembly
Effect of Axial Burnup on Power Distribution and Isotope Inventory for a PWR Fuel S. M. Reda a1 and E. A. Amin b (a) Physics Department, Faculty of Science, Zagazig University, Egypt (b) Nuclear and Radiological
More informationWM2015 Conference, March 15 19, 2015, Phoenix, Arizona, USA
On the Influence of the Power Plant Operational History on the Inventory and the Uncertainties of Radionuclides Relevant for the Final Disposal of PWR Spent Fuel 15149 ABSTRACT Ivan Fast *, Holger Tietze-Jaensch
More informationVerification measurements of alpha active waste
Verification measurements of alpha active waste Bent Pedersen Nuclear Security Unit Directorate Nuclear Safety and Security JRC 9th Edition of the International Summer School on Nuclear Decommissioning
More informationSTATUS OF TRANSMUTATION STUDIES IN A FAST REACTOR AT JNC
STATUS OF TRANSMUTATION STUDIES IN A FAST REACTOR AT JNC Toshio Wakabayashi Japan Nuclear Cycle Development Institute (JNC) 9-13, 1-chome, Akasaka, Minato-ku, Tokyo, Japan Abstract This paper presents
More information2017 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
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 informationPreparation and Testing ORIGEN-ARP Library for VVER Fuel Design
14 Preparation and Testing ORIGEN-ARP Library for VVER Fuel Design Maksym YEREMENKO, Yuriy KOVBASENKO, Yevgen BILODID State Scientific and Technical Centre on Nuclear and Radiation Safety (SSTC NRS), Radgospna
More informationState of the Art for Fuel-Coolant Interactions Research for LFRs. Teodora Retegan, Christian Ekberg, Gunnar Skarnemark
State of the Art for Fuel-Coolant Interactions Research for LFRs Teodora Retegan, Christian Ekberg, Gunnar Skarnemark tretgan@chalmers.se Outline Chalmers Lead Cooled (Fast) Reactors Physical bariers and
More informationTRANSMUTATION PERFORMANCE OF MOLTEN SALT VERSUS SOLID FUEL REACTORS (DRAFT)
15 th International Conference on Nuclear Engineering Nagoya, Japan, April 22-26, 2007 ICONE15-10515 TRANSMUTATION PERFORMANCE OF MOLTEN SALT VERSUS SOLID FUEL REACTORS (DRAFT) Björn Becker University
More informationOptimisation of the Nuclear Reactor Neutron Spectrum for the Transmutation of Am 241 and Np 237
Optimisation of the Nuclear Reactor Neutron Spectrum for the Transmutation of Am 241 and Np 237 Sarah M. Don under the direction of Professor Michael J. Driscoll and Bo Feng Nuclear Science and Engineering
More informationThe Status Report of Plutonium Management in Japan
The Status Report of Plutonium Management in Japan - 215-27 July 216 Office of Atomic Energy Policy Cabinet Office 1. Preface (1) About this report This is a report on the current status of plutonium management
More informationUSE OF LATTICE CODE DRAGON IN REACTOR CALUCLATIONS
USE OF LATTICE CODE DRAGON IN REACTOR CALUCLATIONS ABSTRACT Dušan Ćalić ZEL-EN razvojni center Hočevarjev trg 1 Slovenia-SI8270, Krško, Slovenia dusan.calic@zel-en.si Andrej Trkov, Marjan Kromar J. Stefan
More informationEvaluation and Parameter Analysis of Burn up Calculations for the Assessment of Radioactive Waste 13187
Evaluation and Parameter Analysis of Burn up Calculations for the Assessment of Radioactive Waste 13187 Ivan Fast, Yuliya Aksyutina and Holger Tietze-Jaensch* Product Quality Control Office for Radioactive
More informationIntroduction Discussion i of Fissile il Materials French Pub Nuclear Fuel Cycle
Fundamental Cascade Stage Theory in Isotope Separation for ENU4930/6937: Elements of Nuclear Safeguards, Non-Proliferation, and Security Presented by Glenn E. Sjoden, Ph.D., P.E. Associate Professor and
More informationComparative Study of ADS-burners with Thermal, Intermediate and Fast Neutron Spectrum for Transmutation of Minor Actinides
Comparative Study of ADS-burners with Thermal, Intermediate and Fast Neutron Spectrum for Transmutation of Mor Actides L.I. Ponomarev RRC Kurchatov Institute and MUCATEX, Moscow ~ 90% of radiotoxicity
More informationB. Rouben McMaster University Course EP 4D03/6D03 Nuclear Reactor Analysis (Reactor Physics) 2015 Sept.-Dec.
2: Fission and Other Neutron Reactions B. Rouben McMaster University Course EP 4D03/6D03 Nuclear Reactor Analysis (Reactor Physics) 2015 Sept.-Dec. 2015 September 1 Contents Concepts: Fission and other
More informationPlutonium-Containing Civilian Materials Attractiveness Analysis Using the Figure of Merit Methodology
BgNS TRANSACTIONS volume 20 number 2 (2015) pp. 124 131 Plutonium-Containing Civilian Materials Attractiveness Analysis Using the Figure of Merit Methodology I. Naydenov, K. Filipov Technical University
More informationImplementation 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)
More informationKey Question: What role did the study of radioactivity play in learning more about atoms?
Name Chemistry Essential question: How were the parts of the atom determined? Key Question: What role did the study of radioactivity play in learning more about atoms? Vocabulary: alpha particle fusion
More information