MOx benchmark calculations by deterministic and Monte Carlo codes
Creators
- 1. San Piero a Grado Nuclear Research Group (GRNSPG), University of Pisa, via Diotisalvi 2, 56122 Pisa (Italy)
Description
Highlights: ► MOx based depletion calculation. ► Methodology to create continuous energy pseudo cross section for lump of minor fission products. ► Mass inventory comparison between deterministic and Monte Carlo codes. ► Higher deviation was found for several isotopes. - Abstract: A depletion calculation benchmark devoted to MOx fuel is an ongoing objective of the OECD/NEA WPRS following the study of depletion calculation concerning UOx fuels. The objective of the proposed benchmark is to compare existing depletion calculations obtained with various codes and data libraries applied to fuel and back-end cycle configurations. In the present work the deterministic code NEWT/ORIGEN-S of the SCALE6 codes package and the Monte Carlo based code MONTEBURNS2.0 were used to calculate the masses of inventory isotopes. The methodology to apply the MONTEBURNS2.0 to this benchmark is also presented. Then the results from both code were compared.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2011.10.005Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2011.10.005;
- PII
- S0029-5493(11)00870-3;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 246
- Journal Page Range
- p. 63-68
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- International conference on nuclear energy for new Europe 2010
- Dates
- 6-9 Sep 2010
- Place
- Portoroz (Slovenia)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43078806
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; BURNUP; CROSS SECTIONS; FISSION PRODUCTS; FUEL CYCLE; INVENTORIES; MIXED OXIDE FUELS; MONTE CARLO METHOD; NUCLEAR DATA COLLECTIONS; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; ENERGY SOURCES; FUELS; ISOTOPES; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; SOLID FUELS; URANIUM COMPOUNDS
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.