Nuclear Science and Techniques ›› 2019, Vol. 42 ›› Issue (3): 30602-030602.doi: 10.11889/j.0253-3219.2019.hjs.42.030602

Previous Articles     Next Articles

Development and validation of radiation shielding specialized Monte Carlo software RShieldMC

Jingru HAN,Shengchun SHI,Chong XU,Hongkai WANG(),Jiaxu ZUO,Jianping JING   

  1. 1. Nuclear and Radiation Safety Center, Beijing 100082, China
  • Received:2018-11-26 Revised:2019-02-18 Online:2019-03-10 Published:2019-03-14
  • Contact: Hongkai WANG E-mail:wanghongkai@chinansc.cn
  • About author:<named-content content-type="corresp-name">HAN Jingru</named-content>, female, born in 1983, graduated from North China Electric Power University in 2012, focusing on nuclear reactor physics and shielding review research|<named-content content-type="corresp-name">HAN Jingru</named-content>, female, born in 1983, graduated from North China Electric Power University in 2012, focusing on nuclear reactor physics and shielding review research|WANG Hongkai, E-mail:<email>wanghongkai@chinansc.cn</email>
  • Supported by:
    Supported by National Natural Science Foundation of China(No.11705066);Supported by National Natural Science Foundation of China (No.11705066)

Abstract: Background

Radiation shielding calculation is one of the important contents in nuclear power plant radiation protection design and evaluation. The international shield calculation software implements the “export blockade” on China, which limits the calculation ability of radiation shielding audit.

Purpose

This study aims to develop a dedicate radiation shielding software and verify its validity and correctness in neutron flux calculation.

Methods

First of all, based on Monte-Carlo method, a radiation shielding software, named RShieldMC, was developed. Then the measurement data of Qinshan radiation monitoring tube was used for the code verification. The Qinshan No.1 nuclear plant was modeled via visual modeling software of RShieldMC. The neutron flux of the mid-plane and upper weld in the radiation monitoring tube were calculated by using RShieldMC code.

Results

The calculated results of RShieldMC are in good consistency with the measured values of the radiation monitoring tube test. In addition, the results were also compared with that of MCNP (Monte Carlo N-Particle), JMCT-S (J Monte Carlo transport) and TORT (Three-dimensional Neutron/Photon Transport) programs.

Conclusion

The consistency of the experimental results demonstrates the applicability of RShieldMC in the calculation of neutron flux in PWR.

Key words: Shielding, RShieldMC, Irradiation surveillance capsule

CLC Number: 

  • TL328