Nuclear Science NEA/NSC/R(2016)3 March 2017 www.oecd-nea.org MOx Depletion Calculation Benchmark Unclassified NEA/NSC/R(2016)3 Organisation de Coopération et de Développement Économiques Organisation for Economic Co-operation and Development 21-Mar-2017 ___________________________________________________________________________________________ _____________ English - Or. English NUCLEAR ENERGY AGENCY NUCLEAR SCIENCE COMMITTEE Unclassified NEA/NSC/R(2016)3 MOx Depletion Calculation Benchmark This document exists only in pdf and will be published on the website of the NEA as of 22 March 2017. [email protected] English JT03411102 Complete document available on OLIS in its original format - This document and any map included herein are without prejudice to the status of or sovereignty over any territory, to the delimitation of Or. English international frontiers and boundaries and to the name of any territory, city or area. Nuclear Science MOx Depletion Calculation Benchmark © OECD 2016 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT The OECD is a unique forum where the governments of 35 democracies work together to address the economic, social and environmental challenges of globalisation. The OECD is also at the forefront of efforts to understand and to help governments respond to new developments and concerns, such as corporate governance, the information economy and the challenges of an ageing population. The Organisation provides a setting where governments can compare policy experiences, seek answers to common problems, identify good practice and work to co-ordinate domestic and international policies. 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Requests for permission to photocopy portions of this material for public or commercial use shall be addressed directly to the Copyright Clearance Center (CCC) at [email protected] or the Centre français d'exploitation du droit de copie (CFC) [email protected]. NEA/NSC/R(2016)3 Foreword Under the auspices of the NEA Nuclear Science Committee (NSC), the Working Party on Scientific Issues of Reactor Systems (WPRS) has been established to study the reactor physics, fuel performance, radiation transport and shielding, and the uncertainties associated with modelling of these phenomena in present and future nuclear power systems. The WPRS has different expert groups to cover a wide range of scientific issues in these fields. The Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) was created in 2011 to perform specific tasks associated with reactor physics aspects of present and future nuclear power systems. EGRPANS provides expert advice to the WPRS and the nuclear community on the development needs (data and methods, validation experiments, scenario studies) for different reactor systems and also provides specific technical information regarding: core reactivity characteristics, including fuel depletion effects; core power/flux distributions; Core dynamics and reactivity control. In 2013 EGRPANS published a report that investigated fuel depletion effects in a Pressurised Water Reactor (PWR). This was entitled “International Comparison of a Depletion Calculation Benchmark on Fuel Cycle Issues” NEA/NSC/DOC(2013)1 that documented a benchmark exercise for UO2 fuel rods. This report documents a complementary benchmark exercise that focused on PuO2/UO2 Mixed Oxide (MOX) fuel rods. The results are especially relevant to the back-end of the fuel cycle, including irradiated fuel transport, reprocessing, interim storage and waste repository. Acknowledgements The NEA expresses its sincere gratitude to the authors of the present report, Ms Laurence San Felice, Mr Romain Eschbach, Ms Ratna Dewi Syarifah and Ms Seif-Eddine Maryam, for their valuable contributions to the specifications of the benchmark reported here, the compilation and analysis of the results. Special thanks are extended to Mr Kevin Hesketh for co-ordinating and reviewing the report. 3 NEA/NSC/R(2016)3 Table of contents List of abbreviations and acronyms ........................................................................................ 9 1. Introduction ......................................................................................................................... 10 2. Description of the benchmark ............................................................................................ 12 2.1 Description of SAINT-LAURENT B1 reactor ............................................................... 12 2.2 Geometry and fuel composition data .............................................................................. 13 2.3 Irradiation parameters and history ................................................................................... 17 2.4 Required quantities .......................................................................................................... 18 3. The DARWIN package ....................................................................................................... 19 4. Analysis method .................................................................................................................. 21 5. Participants and codes used ............................................................................................... 22 5.1. CEA ................................................................................................................................ 23 5.2 NNL ................................................................................................................................ 23 5.3. KURCHATOV ............................................................................................................... 23 5.4. GRNSPG (UNIPI) .......................................................................................................... 23 5.5. GRS-KENOREST .......................................................................................................... 24 5.6. GRS-TRITON ................................................................................................................ 25 6. Results and code-to-code comparison for isotopic concentrations ................................. 26 6.1. Actinides results ............................................................................................................. 26 6.2. Fission product results .................................................................................................... 40 6.3. Activation products results ............................................................................................. 45 6.4. Activation-fission product results .................................................................................