Improved mixed oxide fuel calculations with the evaluated nuclear data library JEFF-3.2

Journal Article · Mon Feb 01 00:00:00 EST 2016 · Nuclear Science and Engineering

DOI:https://doi.org/10.13182/NSE15-9· OSTI ID:1261527

Noguere, G.; Bernard, D.; Blaise, P.; Bouland, O.; Leal, Luiz C.; Leconte, P.; Litaize, O.; Peneliau, Y.; Roque, B.; Santamarina, A.; Vidal, J. -F.

In this study, an overestimation of the keff values for mixed oxide (MOX) fuels was identified with Monte Carlo (TRIPOLI-4) and deterministic (APOLLO2) calculations based on the Joint Evaluated Fission and Fusion (JEFF) evaluated nuclear data library. The overestimation becomes sizeable with Pit aging, reaching a reactivity change of Delta(p)similar or equal to+700 pcm for integral measurements carried out with MOX fuel containing a large amount of americium. This bias was observed for various critical configurations performed in the zero power reactor EOLE of the Commissariat a l'energie atomique et aux energies alternatives (CEA), Cadarache, France. The present work focuses on the improvements achieved with the new ²³⁹PU and ²⁴¹Am evaluated nuclear data files available in the latest version of the JEFF library (JEFF-3.2). The resolved resonance range of the plutonium evaluation was reevaluated at Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee, with the Ski/NH code in collaboration with CEA Cadarache. The resonance parameters of the americium evaluation were obtained with the REFIT code in collaboration with the research institutes Institute for Reference Materials and Measurements aRmm, Geel, Belgium, and Institut de recherche sur les lois fondamentales de l'Univers ofio, Saclay, France.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1261527
• Journal Information: Nuclear Science and Engineering, Vol. 182, Issue 2; ISSN 0029-5639
• Publisher: American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
96 KNOWLEDGE MANAGEMENT AND PRESERVATION
EOLE
MIinerve
Tripoli-4
cross-sections
energy-range
reevaluation
validation
code