Characterization of spent PWR fuel for decay heat, neutron and gamma-ray emmission: code comparison

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Abstract

Coupled neutron transport and fuel depletion codes were compared on a simplified reference case of a PWR fuel assembly with initial 235U enrichment of 4% and burnup of 51 GWd/tHM. Two Monte Carlo (MC) codes, Serpent and ALEPH2, and two deterministic codes, SCALE and DRAGON, were considered. A part of the nuclide vector was compared for a cooling period of 5 years. Additionally, observables, measurable by non-destructive analysis methods, i.e. decay heat, neutron and -ray emission rates, were compared as a function of cooling time. The differences between the two MC codes are small, mostly within 1%. The differences in results obtained by deterministic codes are larger, and for production of actinides heavier than plutonium they may reach 7%. The decay heat predictions with Serpent, ALEPH2 and DRAGON agree within 1% for cooling time period 1-1000 years, while the prediction with SCALE module Polaris deviates by around 2% within that cooling time period.

Details

Original languageEnglish
Title of host publicationInternational Conference on Mathematics Computational Methods and Reactor Physics (M&C 2019)
PublisherANS - American Nuclear Society
Pages2736-2745
Edition2019
ISBN (Electronic)978-0-89448-769-9
Publication statusPublished - 1 Sep 2019

Keywords

  • ALEPH2, Depletion analysis, Spent Fuel, code benchmark

ID: 5495395