Analysis of OECD/NEA medium 1000 MWth sodium-cooled fast reactor using the Monte Carlo serpent code and ENDF/B-VIII.0 nuclear data library

Fatima I. Al-Hamadi, Bassam A. Khuwaileh, Peng Hong Liem, Donny Hartanto

Research output: Contribution to journalArticlepeer-review

Abstract

This study presents a benchmark evaluation of the new ENDF/B-VIII.0 nuclear data library for the Organization for Economic Co-operation and Development/Nuclear Energy Agency Medium 1000 MWth sodium-cooled fast reactor (SFR). The study presented herein covers both SFR core types, i.e., metallic fueled (MET-1000) and oxide fueled (MOX-1000), simulated using the continuous-energy Monte Carlo Serpent2 code. The neutronics performances of the ENDF/B-VIII.0-based simulations were compared mainly to two libraries: ENDF/B-VII.1 and JENDL-4.0. The comparison includes several neutronics parameters evaluated for the beginning and end of the cycle conditions. These parameters include the effective multiplication factor keff, total effective delayed neutron fraction βeff, sodium void reactivity (∆ρNa), Doppler constant (∆ρDoppler), and control rod worth (∆ρCR). In addition, a sensitivity study was used to reveal the major isotope/reaction pairs contributing to the discrepancy observed in the performance of the three libraries using 33 and 44-energy-group structures.

Original languageEnglish
Article number121
JournalNuclear Science and Techniques
Volume31
Issue number12
DOIs
StatePublished - Dec 2020
Externally publishedYes

Funding

This work was supported by the Research Institute of Science and Engineering at the University of Sharjah (No. 1802040790-P).

FundersFunder number
Research Institute of Science and Engineering at the University of Sharjah1802040790-P

    Keywords

    • ENDF/B-VIII.0
    • Sensitivity analysis
    • Serpent
    • Sodium-cooled fast reactor

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