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

doi:10.1007/s41365-020-00831-5

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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

NUCLEAR PHYSICS AND INTERDISCIPLINARY RESEARCH | Updated：2021-01-26

- 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
- 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
- 核技术（英文版） 2020年31卷第12期文章编号：121
- Affiliations：
  
  1.Department of Mechanical and Nuclear Engineering, University of Sharjah, P.O. BOX 27272, Sharjah, United Arab Emirates
  2.Cooperative Major in Nuclear Energy, Graduate School of Engineering, Tokyo City University (TCU), 1-28-1 Tamazutsumi, Setagaya, Tokyo, Japan
  3.Scientific Computational Division, Nippon Advanced Information Service (NAIS Co., Inc.), 416 Muramatsu, Tokaimura, Ibaraki, Japan
- Author bio：
  
  Corresponding author, dhartanto@sharjah.ac.ae
- Funds：
  
  Research Institute of Science and Engineering at the University of Sharjah
- DOI：10.1007/s41365-020-00831-5
  中图分类号：
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Fatima I. Al-Hamadi, Bassam A. Khuwaileh, Peng Hong Liem, 等. 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[J]. 核技术（英文版）, 2020,31(12):121

Fatima I. Al-Hamadi, Bassam A. Khuwaileh, Peng Hong Liem, et al. 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[J]. Nuclear Science and Techniques, 2020,31(12):121
Fatima I. Al-Hamadi, Bassam A. Khuwaileh, Peng Hong Liem, 等. 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[J]. 核技术（英文版）, 2020,31(12):121 DOI： 10.1007/s41365-020-00831-5.

Fatima I. Al-Hamadi, Bassam A. Khuwaileh, Peng Hong Liem, et al. 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[J]. Nuclear Science and Techniques, 2020,31(12):121 DOI： 10.1007/s41365-020-00831-5.

摘要

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 ,k,eff, total effective delayed neutron fraction β ,eff, sodium void reactivity (∆ρ,Na,), Doppler constant (∆ρ,Doppler,), and control rod worth (∆ρ,CR,). 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.

关键词

Keywords

SerpentENDF/B-VIII.0Sodium-cooled fast reactorSensitivity analysis

references

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