0
research-article

Verification and Validation of SuperMC 3.2 using VENUS-3 Benchmark Experiments

[+] Author and Article Information
Isaac Kwasi Baidoo

Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031, China; University of Science and Technology of China, Hefei, Anhui, 230027, China
isaac.baidoo@fds.org.cn

Jun Zou

Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031, China
jun.zou@fds.org.cn

Bin Li

Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031, China
bin.li@fds.org.cn

Jing Song

Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031, China
jing.song@fds.org.cn

Bin Wu

Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031, China
bin.wu2@fds.org.cn

Qi Yang

Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031, China
qi.yang@fds.org.cn

Zhumin Zhao

Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031, China
zhumin.zhao@fds.org.cn

1Corresponding author.

ASME doi:10.1115/1.4043100 History: Received November 27, 2018; Revised February 21, 2019

Abstract

Methodological processes for Nuclear Power Plant Pressure Vessels' (PV) neutron fluence rate determination take the form of experimental measurement or theoretical calculations. However, the process of experimental measurement takes longer period, as it requires incorporation of surveillance capsules into PV system undergoing normal NPP operation. Therefore, strong reliance on computation and modeling of radiation-induced degradation is given much attention. In this work, the VENUS-3 benchmark has been analyzed with SuperMC code, with the intention of validating SuperMC for accurate reactor neutronics; dosimetry response calculations for in-core/ex-core structural components, particularly with respect to the VENUS-3 configuration type (PWRs). Complete 3D geometry and source modeling for VENUS-3 facility has been developed. Neutron transport and calculations of equivalent fission flux for the experimental target quantities; 115In (n, n'), 58Ni (n, p) and 27Al (n, a) is also achieved. The calculation results show good agreement with the experimental measurement. Greater majority of the calculated values (C/E) were within the required accuracy of ±10% for reactor components' dosimetry calculations; most of these values were contained within 5% deviation from the experimental data. Additional calculations and detailed analysis for fast neutron flux distribution, iron displacement per atom rate (dpa/s), including characteristic effect of partial length assembly (PLSA) on VENUS-3 core barrel is also discussed. It is therefore evidenced that, the effectiveness of SuperMC code for in-core/ex-core reactor neutronics computations have been demonstrated through the VENUS-3 benchmark testing.

Copyright (c) 2019 by ASME
Your Session has timed out. Please sign back in to continue.

References

Figures

Tables

Errata

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In