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Technical Brief

Simulation Calculation of the Core Physical Characteristics of China Experimental Fast Reactor with MCNP

[+] Author and Article Information
Wenbin Xiong

Nuclear and Radiation Safety Center, MEP of China, No.54 of Hong Lian Nan Cun, Haidian, Beijing, China, 10082
xiongwenbin@chinansc.cn

Qin Xie

School of Nuclear Science and Technology University of South China, 28 Western Changshen Road, Hengyang City, Hunan Province, China, 421001
zoid0@hotmail.com

Huwei Li

Nuclear and Radiation Safety Center, MEP of China, No.54 of Hong Lian Nan Cun, Haidian, Beijing, China, 10082
lihuwei@chinansc.cn

Sengai Yang

Nuclear and Radiation Safety Center, MEP of China, No.54 of Hong Lian Nan Cun, Haidian, Beijing, China, 10082
yangsengai@chinansc.cn

Huan Mao

Nuclear and Radiation Safety Center, MEP of China, No.54 of Hong Lian Nan Cun, Haidian, Beijing, China, 10082
maohuan@chinansc.cn

Jian Cao

Nuclear and Radiation Safety Center, MEP of China, No.54 of Hong Lian Nan Cun, Haidian, Beijing, China, 10082
caojian@chinansc.cn

1Corresponding author.

ASME doi:10.1115/1.4038999 History: Received September 03, 2017; Revised December 21, 2017

Abstract

The whole core model of CEFR is established according to the parameters of China Experimental Fast Reactor which are given by IAEA-TECDOC-1531, and the physical parameters of CEFR are simulated with the MCNP4a program. The calculation results are compared with the data contained in the safety analysis report of CEFR. The calculation results are consistent with the design values, which successfully demonstrates the acceptable fidelity of the MCNP model. The MCNP model will be further refined and applied for nuclear safety review of the CEFR in the future.

Copyright (c) 2018 by ASME
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