Sensitivity and uncertainty based techniques to extend the database of experimental validation benchmarks: practical example of use for TRIGA fuel
Creators
- 1. Framatome - 10, Rue Juliette Recamier, 69006 Lyon (France)
- 2. Framatome - ZI les Berauds BP 1114, 26104 Romans sur Isere (France)
- 3. Institut de Radioprotection et de Surete Nucleaire - IRSN, PSN-EXP/SNC, B.P. 17 - 92262, Fontenay-aux-Roses (France)
Description
Analysis of sensitivity profiles and covariance data provides a robust mathematical approach towards assessing the similarity of experimental benchmarks that can be used for validation of criticality calculations. This approach is all the more valuable when dealing with fissile materials for which only a small number of experimental benchmarks exist, since it makes it possible to select other relevant experiments performed with different fissile materials. A practical example of Framatome industrial application is performed on TRIGA fuel, used worldwide in research nuclear reactors. The fissile material of such fuel elements is a metallic alloy of UZrHx intrinsically moderated with an atomic ratio of H/Zr close to 1.6 and a U content ranging between 8 and 47 wt.%, with 20 wt.% enrichment. The experimental validation of such media is typically based on a very small number of ICSBEP (International Criticality Safety Benchmark Evaluation Project) experimental configurations (mainly IEU-COMP-THERM-003). However, the analysis of sensitivity profiles, as well as the contribution of each reaction to prior uncertainty using various covariance data helps pointing out other ICSBEP benchmarks of interest. These experiments can then be used to extend the experimental validation database and justify the bias due to nuclear data and calculation scheme for criticality calculations performed with the French criticality safety code package CRISTAL. Those calculations, currently performed with the TSUNAMI/TSURFER sensitivity/uncertainty sequence of the SCALE package, show the potential industrial interest in these approaches. They also highlight the need to develop in-house expertise in the domain, as well as tools more consistent with CRISTAL package such as MACSENS, currently under development at IRSN. This paper shows an industrial practical application of sensitivity and similarity techniques, namely the extension of the validation database for UZrH TRIGA fuel. The method proves to be useful by quantifying the similarity with a large number of available benchmarks
Files
Additional details
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- INIS-FR--21-0154
Conference
- Title
- 11. international conference on nuclear criticality safety
- Acronym
- ICNC 2019
- Dates
- 15-20 Sep 2019
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 52011530
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; BENCHMARKS; CRITICALITY; NUCLEAR FUELS; SAFETY ANALYSIS; SENSITIVITY ANALYSIS; TRIGA TYPE REACTORS
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MATERIALS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses