1/12 VUJE, Inc., Okružná 5, SK 918 64 Trnava, Slovakia Plutonium and MA Management in VVER-440 and FR P. Dařílek, R. Zajac – VUJE Trnava

Slides:



Advertisements
Similar presentations
Fuel Cycle Subcommittee: Overview and Status Fusion-Fission Hybrid Workshop Gaithersburg, MD September 30, 2009 Robert N. Hill Department Head – Nuclear.
Advertisements

Text optional: Institutsname Prof. Dr. Hans Mustermann Mitglied der Leibniz-Gemeinschaft Partitioning & Transmutation Combined with Molten Salt.
NUCLEAR FUSION & NUCLEAR FISSION Noadswood Science, 2012.
Nuclear Fuel Production Fissile Nuclei Uranium and Plutonium 235 U 239 Pu.
Investigation of "dry" recriticality of the melt during late in-vessel phase of severe accident in Light Water Reactor D.Popov, KNPP, BG O.Runevall, KTH,
Nuclear Fuel Production Fissile Nuclei Uranium and Plutonium 235 U 239 Pu.
High Support Ratio Fusion-Fission Hybrid System ~ Fuel Cycles Swadesh Mahajan for The Texas Group DOE Fusion-Fission Hybrid Workshop Sept.30-Oct2, 2009.
SABR FUEL CYCLE C. M. Sommer, W. M. Stacey, B
L. Tassan-Got – IPN Orsay Nuclear data and reactor physics Radiotoxicity and spent fuel.
Nuclear Energy Targets: Explain how the nuclear fuel cycle relates to the true cost of nuclear energy and the disposal of nuclear waste. Describe the issues.
 Benefits of Nuclear Energy  How Fission Works  Nuclear Power Plant Basics  Overview of Uranium Fuel Cycle  Energy Lifecycle of Nuclear Power  Generation.
Государственный научный центр Научно-исследовательский институт атомных реакторов Alexander V. Bychkov Director Research Institute of Atomic Reactors Dimitrovgrad,
Fuel Cycle – High Level Waste Disposal
А Е Ц “К О З Л О Д У Й” - Е А Д N P P K O Z L O D U Y – P L C 17 th Symposium of AER Y alta, Crimea, September 24-28, 2007 WWER-1000 SPENT FUEL NUCLIDE.
Copyright © 2012 SCKCEN 3 rd LEADER International workshop Pisa & Bologna, 4-7 September 2012 Didier De Bruyn (SCKCEN) 1 Different ADS concepts in the.
Fundamentals of Neutronics : Reactivity Coefficients in Nuclear Reactors Paul Reuss Emeritus Professor at the Institut National des Sciences et Techniques.
Fusion-Fission Hybrid Systems
核工程计算物理实验室 Nuclear Engineering Computational Physics The Neutronics Studies of Fusion Fission Hybrid Power Reactor Youqi Zheng Ph. D Nuclear.
Future perspectives of nuclear energy
Environment Institute Where ideas grow atomexpo 2013 forum: “Nuclear energy and public acceptance”, Saint Petersburg, 28 June 2013 Plentiful Energy – key.
The Nuclear Fuel Cycle Dr. Okan Zabunoğlu Hacettepe University Department of Nuclear Engineering.
Transmutations of Actinides in Fusion-Fission Hybrids – a Model Nuclear Synergy ? Stefan Taczanowski Faculty of Energy and Fuels AGH University of Science.
Complex Approach to Study Physical Features of Uranium Multiple Recycling in Light Water Reactors A.A. Dudnikov, V.A. Nevinitsa, A.V. Chibinyaev, V.N.
Can Thermal Reactor Recycle Eliminate the Need for Multiple Repositories? C. W. Forsberg, E. D. Collins, C. W. Alexander, and J. Renier Actinide and Fission.
MA and LLFP Transmutation Performance Assessment in the MYRRHA eXperimental ADS P&T: 8th IEM, Las Vegas, Nevada, USA November 9-11, 2004 E. Malambu, W.
Nuclear Energy By: Elisa Fatila April 6, 2006.
Antineutrino Monitoring of Reactors Theoretical Feasibility Studies Antineutrino Monitoring of Reactors Theoretical Feasibility Studies Michael Nieto,
MODELLING OF THE VVER-440 REACTOR FOR DETERMINATION OF THE SPATIAL WEIGHT FUNCTION OF EX-CORE DETECTORS USING MCNP-4C2 CODE Gabriel Farkas, Vladimír Slugeň.
3. Core Layout The core loading pattern for the proliferation resistant advanced transuranic transmuting design (PRATT) was optimized to obtain an even.
4/2003 Rev 2 I.4.9j – slide 1 of 18 Session I.4.9j Part I Review of Fundamentals Module 4Sources of Radiation Session 9jFuel Cycle – High Level Waste Disposal.
1 prezentácia VUJE, Inc., Okružná 5, Trnava, Slovak Republic K. Klučárová, J. Remiš, M. Závodský, V. Petényi VUJE, Inc. 17th Symposium of AER, Sept.
Reduction of Spent Fuel Volume by Optimisation of VVER- 440 Fuel Assembly AER Meeting, Working Group F Liblice, Czech Republic April 10 – 12,
1 Massimo SALVATORESiemtp 8 – November th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation University.
Liquid Metal Fast Breeder Reactors Martin W. Metzner November 19, 2007.
1 RRC KI Reduced leakage 17th Symposium of AER on VVER Reactor Physics and Reactor Safety September 24-29, 2007, Yalta, Crimea, Ukraine ADVANCED FUEL CYCLES.
Advanced Heavy Water Reactor Amit Thakur Reactor Physics Design Division Bhabha Atomic Research Centre, INDIA.
FAST MOLTEN SALT REACTOR –TRANSMUTER FOR CLOSING NUCLEAR FUEL CYCLE ON MINOR ACTINIDES A.Dudnikov, P.Alekseev, S.Subbotin.
AERB Safety Research Institute 1 TIC Benchmark Analysis Subrata Bera Safety Research Institute (SRI) Atomic Energy Regulatory Board (AERB) Kalpakkam –
USE OF THE AXIAL BURNUP PROFILE AT THE NUCLEAR SAFETY ANALYSIS OF THE VVER-1000 SPENT FUEL STORAGE FACILITY IN UKRAINE Olena Dudka, Yevgen Bilodid, Iurii.
Characteristics of Transmutation Reactor Based on LAR Tokamak Neutron Source B.G. Hong Chonbuk National University.
Chapter 11 Nuclear Power  Energy released in combustion reactions comes from changes in the chemical bonds that hold the atom together.  Nuclear Energy.
Potential role of FF hybrids Massimo Salvatores CEA-Cadarache- France Fusion-Fission Hybrids have a potential role (in principle and independently from.
A U.S. Department of Energy Office of Science Laboratory Operated by The University of Chicago Nuclear Engineering Division Argonne National Laboratory.
FP 6 Integrated Project: FUETRA Proposal TWG-ADS Roadmap, Fuel Cycle sub-group report recommendations, Fuel Cycle studies (CEA, ITU, NEA...) EFTTRA collaboration.
The Nuclear Fuel industry The nuclear fuel cycle.
2016 January1 Nuclear Options for the Future B. Rouben McMaster University EP4P03_6P03 Nuclear Power Plant Operation 2016 January-April.
D J Coates, G T Parks Department of Engineering, University of Cambridge, UK 3 rd Year PhD student Actinide Breeding and Reactivity Variation in a Thermal.
Nuclear Fuel Production Fissile Nuclei Uranium and Plutonium 235 U 239 Pu.
Process modelling and optimization aid FONTEIX Christian Professor of Chemical Engineering Polytechnical National Institute of Lorraine Chemical Engineering.
The Uranium Fuel Cycle Robert Tsai November 21, 2006.
Adonai Herrera-Martínez, Yacine Kadi, Geoff Parks, Vasilis Vlachoudis High-Level Waste Transmutation: Thorium Cycle vs Multi-Tier Strategy.
NEAR-COMPLETE TRANSURANIC WASTE INCINERATION IN THORIUM-FUELLED LIGHT WATER REACTORS Ben Lindley.
1/10 VUJE, Inc., Okružná 5, Trnava, Slovakia; FEI STU, Ilkovičova 3, Bratislava, Slovakia Thorium Fuel Cycle Under VVER and PWR Conditions.
Nuclear Radiation NC Essential Standard Types of Radiation, Penetrating Ability of Radiation, Nuclear Equations, Nuclear Decay, Half-Life, Fission.
Project guide By Dr.V.Mahesh T. Bhargav Dean(Research)
Study on Neutronics of plutonium and Minor Actinides Transmutation in Accelerator Driven System Reactor By Amer Ahmed Abdullah Al-Qaaod Ph.D student Physics.
New radiochemical technologies of spent nuclear fuel reprocessing
Nuclear Energy and the Environment
How precisely do we know the antineutrino source spectrum from a nuclear reactor? Klaus Schreckenbach (TU München) Klaus Schreckenbach.
Nuclear Fuel Production Fissile Nuclei Uranium and Plutonium
Pebble Bed Reactors for Once Trough Nuclear Transmutation
Sensitivity analysis in burnup calculations with Monte Carlo
Improvements of Nuclear Fuel Cycle Simulation System (NFCSS) at IAEA
3rd Workshop on dynamic fuel cycle Timothée Kooyman, DEN,DR,SPRC,LE2C
Daniel Wojtaszek 3rd Technical Workshop on Fuel Cycle Simulation
Nuclear Fuel Production Fissile Nuclei Uranium and Plutonium
Cross Section Versus Recipes for Fuel Cycle Transition Analysis
Approaches to Evaluation of Spent Nuclear
Prospective inventory of radioactive materials
Presentation transcript:

1/12 VUJE, Inc., Okružná 5, SK Trnava, Slovakia Plutonium and MA Management in VVER-440 and FR P. Dařílek, R. Zajac – VUJE Trnava J. Breza, V Nečas – SUT Bratislava

2/12 VUJE, Inc., Okružná 5, SK Trnava, Slovakia Content  VVER-440  Description of analysed cycles VVER-440 open fuel cycle VVER-440 closed fuel cycle with IMF FR closed fuel cycle  Cycle comparison  Conclusion

3/12 VUJE, Inc., Okružná 5, SK Trnava, Slovakia VVER-440 Standard uranium FA of VVER-440  PWR reactor  power 440 MW el  triangular net  „black“ control rods  hexagonal fuel assembly

4/12 VUJE, Inc., Okružná 5, SK Trnava, Slovakia VVER-440 open fuel cycle description  reference case  feeding enrichment 4.2 % U235  no reprocessing

5/12 VUJE, Inc., Okružná 5, SK Trnava, Slovakia VVER-440 closed fuel cycle with IMF description

6/12 VUJE, Inc., Okružná 5, SK Trnava, Slovakia VVER-440 closed fuel cycle with IMF description Transmutation pin with inert matrix fuel Fresh UOX pin with 4.2% U235 enrichment VVER-440 combined fuel assembly (CFA)  microheterogeneous assembly  30 transmutation pins (TP) with: 6.17 wt.% Pu oxides 0.77 wt.% MA oxides from CFA UP reprocessing

7/12 VUJE, Inc., Okružná 5, SK Trnava, Slovakia VVER-440 closed fuel cycle with IMF description wt. content (%) NpO PuO AmO CmO CfO ZrO isotopecontent (%)isotopecontent (%) Pu Cm Pu Cm Pu Cm Pu Cm Pu Cm Cm Cm isotopecontent (%)isotopecontent (%) Am Cf Am Cf Am-242m0.23Cf Cf Detailed composition of fresh TP  reprocessing of all UPs  all Pu and MA into TPs  no TP reprocessing  equilibrium cycle without UOX core

8/12 VUJE, Inc., Okružná 5, SK Trnava, Slovakia FR closed fuel cycle description

9/12 VUJE, Inc., Okružná 5, SK Trnava, Slovakia FR closed fuel cycle description Fast reactor fuel assembly (FFA) Super Phenix FA content (% of HM) U Np0.097 Pu Am1.623 Cm0.977 Cf0.003 U isotopecontent (%) isotopecontent (%) Pu Cm Pu Cm Pu Cm Pu Cm Pu Cm Cm Cm isotopecontent (%) isotopecontent (%) Am Cf Am Cf Am- 242m 2.89Cf Cf

10/12 VUJE, Inc., Okružná 5, SK Trnava, Slovakia Cycle comparison Fuel cycle Units VVER-440 open VVER- 440 IMF FR Pu transmutation ratekg/TWh e MA transmutation ratekg/TWh e Pu and MA rate in entering fuel% Pu and MA rate in spent fuel% Quantity of separated Pukg/TWh e Content of (Pu 239 +Pu 241 ) in separated Pu% Inventory of Pu in cycle incl.corekg/TWh e Content of (Pu 239 +Pu 241 ) in burned fuel% Amount of finally disposed of Pukg/TWh e Pu and MA balance

11/12 VUJE, Inc., Okružná 5, SK Trnava, Slovakia Conclusion Comparison of closed cycles  comparable Pu transmutation rate  fissionable Pu content in spent IMF very low  Pu amount in FR cycle much higher  MA transmuted 4-times faster in FR  finally disposed Pu amount 70-times smaller

12/12 VUJE, Inc., Okružná 5, SK Trnava, Slovakia Acknowledgements Performance of mentioned analyses could not be possible without participation of VUJE and SUT at the RED-IMPACT project. We want to acknowledge especially valuable advise and notes of project and WP leaders W. Gudowski, W.v. Lensa, D. Greneche, L. Boucher and C. Zimmermann. This project has been partially supported by the Slovak grant agency for science through the grant No. 1/3160/06.