On the Validation of VESTA 2.2.0 Using the ARIANE-GU3 Sample
Creators
- 1. IRSN, PSN-EXP/SNC/LN 31 avenue de la Division Leclerc, Fontenay-aux-Roses (France)
Description
The validation of the VESTA 2.2.0 Monte Carlo depletion code has been initiated using the Spent Fuel Isotopic Composition Database (SFCOMPO). The work presented in this paper is limited to one fuel sample, the GU3 PWR-UOX sample from the ARIANE program, which has a reported burn up of 52.5 MWd.kgHM-1. The chemical analyses of the studied fuel sample were performed by 2 independent laboratories at the end of irradiation and cooling time. US and European evaluated nuclear data libraries, namely ENDF/B-VII.1 and JEFF-3.2, but also the more recent ENDF/B-VIII.0 and JEFF-3.3 are used for the VESTA 2.2.0 calculations. The isotopic concentration results are compared to experimental data and the C/E agreement is analyzed in the light of the previous VESTA 2.1.5 validation results obtained using ENDF/B-VII.0 and JEFF-3.1 nuclear data libraries.
Availability note (English)
Available from https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_10005.pdf; https://doaj.org/article/1ab4e42275804d80b36ec171274e1a64Additional details
Identifiers
Publishing Information
- Journal Title
- EPJ. Web of Conferences
- Journal Volume
- 247
- Journal Page Range
- vp.
- ISSN
- 2100-014X
Conference
- Title
- International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
- Acronym
- PHYSOR2020
- Dates
- 28 Mar - 2 Apr 2020
- Place
- Cambridge (United Kingdom)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 53087803
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CHEMICAL ANALYSIS; COOLING TIME; IRRADIATION; ISOTOPE RATIO; MONTE CARLO METHOD; NUCLEAR DATA COLLECTIONS; PWR TYPE REACTORS; SPENT FUELS
- Descriptors DEC
- CALCULATION METHODS; DIMENSIONLESS NUMBERS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS