The independent verification calculation of leader factor of reactor surveillance capsule

LIU Qiaofeng; HAN Jingru; ZHAO Chuanqi; CHEN Haiying; WU Yongle

doi:10.11889/j.0253-3219.2019.hjs.42.090601

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The independent verification calculation of leader factor of reactor surveillance capsule

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2024-10-25

- The independent verification calculation of leader factor of reactor surveillance capsule
- NUCLEAR TECHNIQUES Vol. 42, Issue 9, Article number: 090601(2019)
- 作者机构：
  
  生态环境部核与辐射安全中心北京 100082
- 作者简介：
  
  LIU Qiaofeng, female, born in 1985, graduated from China Institute of Atomic Energy with a doctoral degree in 2015, focusing on radiation and environmental protection
  WU Yongle, E-mail: wuyongle@chinansc.cn
- 基金信息：
- DOI：10.11889/j.0253-3219.2019.hjs.42.090601
  CLC： TL48
- Received：01 April 2019，
  
  Revised：02 July 2019，
  
  Published：10 September 2019
- 稿件说明：
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刘巧凤,韩静茹,赵传奇等.反应堆辐照监督管超前因子的独立审核计算[J].核技术,2019,42(09):67-72.

LIU Qiaofeng,HAN Jingru,ZHAO Chuanqi,et al.The independent verification calculation of leader factor of reactor surveillance capsule[J].NUCLEAR TECHNIQUES,2019,42(09):67-72.
刘巧凤,韩静茹,赵传奇等.反应堆辐照监督管超前因子的独立审核计算[J].核技术,2019,42(09):67-72. DOI： 10.11889/j.0253-3219.2019.hjs.42.090601.

LIU Qiaofeng,HAN Jingru,ZHAO Chuanqi,et al.The independent verification calculation of leader factor of reactor surveillance capsule[J].NUCLEAR TECHNIQUES,2019,42(09):67-72. DOI： 10.11889/j.0253-3219.2019.hjs.42.090601.

摘要

辐照监督管超前因子是反应堆压力容器材料监督过程中的一项重要指标，为预测反应堆压力容器寿命的关键参数之一。对反应堆辐照监督管超前因子开展独立审核计算，能够有效评估反应堆设计值的准确性，提高核安全审评的独立性、科学性和有效性。针对某三代压水堆，采用蒙特卡罗方法计算程序对反应堆辐照监督管超前因子进行独立审核计算。结果表明：该压水堆的超前因子计算结果与反应堆设计值的相对偏差在5%以内，满足核安全审评的要求，为该三代压水堆核电厂的核安全审评提供技术支持。

Abstract

Background

Leader factor of surveillance capsule is an important indicator in the reactor pressure vessel material supervision process

and is one of the key parameters for predicting of the lifetime of reactor pressure vessel.

Purpose

This study aims at independent verification calculation of the leader factor of reactor surveillance capsule so as to evaluate the accuracy of the reactor design

and improve the independence

scientificality

and effectiveness of the nuclear safety review.

Methods

Monte Carlo calculation program was employed to calculate the main factors of a three-generation pressurized water reactor (PWR) reactor monitoring cabin. Both the maximum fast neutron fluence at the inner surface of pressure vessel and fast neutron fluxes at samples in irradiation supervisory tubes were verified and calculated.

Results

The results showed that the relative deviations between the calculated results and the design values were less than 5%

and the leader factors could comply with the requirement of the nuclear safety review.

Conclusion

This work provides a reference for nuclear safety review and design departments of nuclear power plants. The calculation results provide effective technical support for nuclear safety review of the third-generation PWR nuclear power plant.

关键词

Keywords

references

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