Nuclear data requirements for the ADS conceptual design EFIT: Uncertainty and sensitivity study
Creators
- 1. Instituto de Fusion Nuclear, Universidad Politecnica de Madrid (Spain)
- 2. Departamento de Ingenieria Nuclear, Universidad Politecnica de Madrid (Spain)
- 3. CIEMAT (Spain)
- 4. Departamento de Ingenieria Energetica, UNED (Spain)
- 5. Laboratorio de Estadistica, Universidad Politecnica de Madrid (Spain)
Description
In this paper, we assess the impact of activation cross-section uncertainties on relevant fuel cycle parameters for a conceptual design of a modular European Facility for Industrial Transmutation (EFIT) with a 'double strata' fuel cycle. Next, the nuclear data requirements are evaluated so that the parameters can meet the assigned design target accuracies. Different discharge burn-up levels are considered: a low burn-up, corresponding to the equilibrium cycle, and a high burn-up level, simulating the effects on the fuel of the multi-recycling scenario. In order to perform this study, we propose a methodology in two steps. Firstly, we compute the uncertainties on the system parameters by using a Monte Carlo simulation, as it is considered the most reliable approach to address this problem. Secondly, the analysis of the results is performed by a sensitivity technique, in order to identify the relevant reaction channels and prioritize the data improvement needs. Cross-section uncertainties are taken from the EAF-2007/UN library since it includes data for all the actinides potentially present in the irradiated fuel. Relevant uncertainties in some of the fuel cycle parameters have been obtained, and we conclude with recommendations for future nuclear data measurement programs, beyond the specific results obtained with the present nuclear data files and the limited available covariance information. A comparison with the uncertainty and accuracy analysis recently published by the WPEC-Subgroup26 of the OECD using BOLNA covariance matrices is performed. Despite the differences in the transmuter reactor used for the analysis, some conclusions obtained by Subgroup26 are qualitatively corroborated, and improvements for additional cross sections are suggested.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2010.06.006Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2010.06.006;
- PII
- S0306-4549(10)00208-2;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 37
- Journal Issue
- 11
- Journal Page Range
- p. 1570-1579
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 42010493
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCELERATOR BREEDERS; ACCELERATOR DRIVEN TRANSMUTATION; ACCURACY; ACTINIDES; BURNUP; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CROSS SECTIONS; DESIGN; FUEL CYCLE; MONTE CARLO METHOD; NUCLEAR DATA COLLECTIONS; SENSITIVITY ANALYSIS; SPENT FUELS; URANIUM NITRIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; ELEMENTS; ENERGY SOURCES; EVALUATION; FUELS; MATERIALS; METALS; NITRIDES; NITROGEN COMPOUNDS; NUCLEAR FUELS; PNICTIDES; REACTOR MATERIALS; SIMULATION; TRANSMUTATION; URANIUM COMPOUNDS
Optional Information
- Copyright
- Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.