反应堆辐照监督管超前因子的独立审核计算

刘巧凤; 韩静茹; 赵传奇; 陈海英; 吴永乐

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

您当前的位置：

首页 >

文章列表页 >

反应堆辐照监督管超前因子的独立审核计算

核能科学与工程 | 更新时间：2024-10-25

- 反应堆辐照监督管超前因子的独立审核计算
- The independent verification calculation of leader factor of reactor surveillance capsule
- 核技术 2019年42卷第9期文章编号：090601
- 作者机构：
  
  生态环境部核与辐射安全中心北京 100082
- 作者简介：
  
  刘巧凤，女，1985年出生，2015年于中国原子能科学研究院获博士学位，研究领域为辐射防护及环境保护
  吴永乐，E-mail：wuyongle@chinansc.cn
- 基金信息：
  
  国家科技重大专项(2017ZX06004002-001)
- DOI：10.11889/j.0253-3219.2019.hjs.42.090601
  中图分类号： TL48
- 收稿日期：2019-04-01，
  
  修回日期：2019-07-02，
  
  纸质出版日期：2019-09-10
- 稿件说明：
移动端阅览
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

ASTM E185-02 . Standard practice for design of surveillance programs for light-water moderated nuclear power reactor vessels [S ] . 2002 .

环境保护部核电安全监管司. 环境保护部核与辐射安全中心译 . 美国核管理委员会NUREG-0800核电厂安全分析报告标准审查大纲 [M ] . 北京 : 中国原子能出版社 , 2017 .

Department of Nuclear Power Safety Regulation of MEP . Nuclear and Radiation Safety Center of MEP . U.S. Nuclear Regulatory Commission NUREG-0800 standard review plan for the review of safety analysis reports [M ] . Beijing : China Atomic Energy Press , 2017 .

U.S. Nuclear Regulatory Commission. NUREG-0800, standard review plan for the review of safety analysis reports for nuclear power plants LWR edition [R ] . 2007 .

U.S. Nuclear Regulatory Commission. Reactor vessel material surveillance program requirements-appendix H to 10 CFR Part 50 [R ] . 2009 .

ASTM E185-82 . Standard practice for design of surveillance programs for light-water moderated nuclear power reactor vessels [S ] . 1982 .

邓理邻 , 吕焕文 , 谭怡 , 等 . 辐照监督管中子注量率精细化模型计算方法研究 [J ] . 核动力工程 , 2013 , 34 (增刊 1 ): 84 - 86 . DOI: 10.3969/j.issn.0258-0926.2013.z1.020 http://dx.doi.org/10.3969/j.issn.0258-0926.2013.z1.020 .

DENG Lilin , LYU Huanwen , TAN Yi , et al . Research on theoretical calculation method for refined modeling of fast neutron fIux in irradiation surveillance capsule [J ] . Nuclear Power Engineering , 2013 , 34 (s 1 ): 84 - 86 . DOI: 10.3969/j.issn.0258-0926.2013.z1.020 http://dx.doi.org/10.3969/j.issn.0258-0926.2013.z1.020 .

石秀安 , 苏耿华 , 包鹏飞 . 压水堆辐照监督管中子注量计算方法改进研究 [J ] . 核科学与工程 , 2018 , 38 ( 4 ): 585 - 589 .

SHI Xiuan , SU Genghua , BAO Pengfei . Study on the improvement of calculation method for the neutron fluence in the irradiation monitoring tube of the reactor vessel [J ] . Nuclear Science and Engineering , 2018 , 38 ( 4 ): 585 - 589 .

张斌 , 郑君萧 , 李晓静 , 等 . 反应堆压力容器快中子注量计算不确定性分析 [J ] . 核技术 , 2018 , 41 ( 2 ): 020605 . DOI: 10.11889/j.0253-3219.2018.hjs.41.020605 http://dx.doi.org/10.11889/j.0253-3219.2018.hjs.41.020605 .

ZHANG Bin , ZHENG Junxiao , LI Xiaojing , et al . Uncertainty analysis of reactor pressure vessel fast neutron fluence calculation [J ] . Nuclear Techniques , 2018 , 41 ( 2 ): 020605 . DOI: 10.11889/j.0253-3219.2018.hjs. 41.020605 http://dx.doi.org/10.11889/j.0253-3219.2018.hjs. 41.020605 .

夏春梅 , 梅其良 , 丁谦学 , 等 . DORT程序进行RPV中子注量率计算的可靠性验证 [J ] . 核科学与工程 , 2016 , 36 ( 3 ): 329 - 334 . DOI: 10.3969/j.issn.0258-0918.2016. 03.005 http://dx.doi.org/10.3969/j.issn.0258-0918.2016. 03.005 .

XIA Chunmei , MEI Qiliang , DING Qianxue , et al . Reliability validation of RPV neutron flux calculated by DORT [J ] . Nuclear Science and Engineering , 2016 , 36 ( 3 ): 329 - 334 . DOI: 10.3969/j.issn.0258-0918.2016.03.005 http://dx.doi.org/10.3969/j.issn.0258-0918.2016.03.005 .

Los Alamos National Laboratory. MCNP - a general Monte Carlo N-particle transport code [R ] . Version 5 . 2003 .

杨玉中 . 基于蒙特卡罗输运技术的压力容器及辐照监督管中子注量计算方法研究及应用 [C ] . 中国核学会计算物理学会第十届反应堆数值计算和粒子输运学术会议暨2004年反应堆物理会议 , 2004 : 535 - 543 .

YANG Yuzhong . The research and application on calculation of neutron flux for pressure vessel and irradiation surveillance capsule based on Monte Carlo transport technology [C ] . The 10th Academic Conference of Reactor Numerical Calculation and Particle Transport and 2004 Reactor Physics Conference of Computational Physics Society of Chinese Nuclear Society , 2004 : 535 - 543 .

刘巧凤 , 韩静茹 , 陈海英 , 等 . 反应堆压力容器快中子注量计算模型简化方法研究 [J ] . 核电子学与探测技术 , 2015 , 35 ( 12 ): 1201 - 1204 . DOI: 10.3969/j.issn.0258-0934.2015.12.011 http://dx.doi.org/10.3969/j.issn.0258-0934.2015.12.011 .

LIU Qiaofeng , HAN Jingru , CHEN Haiying , et al . Study on simplification calculation methods of reactor pressure vessel fast neutron flux [J ] . Nuclear Electronics & Detection Technology , 2015 , 35 ( 12 ): 1201 - 1204 . DOI: 10.3969/j.issn.0258-0934.2015.12.011 http://dx.doi.org/10.3969/j.issn.0258-0934.2015.12.011 .

刘同先 , 赵禹 , 曹欣荣 . MCNP程序评价压力容器中子注量率结果研究 [C ] . 第十一届反应堆数值计算和粒子输运学术会议暨2006年反应堆物理会议 , 2006 : 666 - 675 .

LIU Tongxian , ZHAO Yu , CAO Xinrong . Research on evaluation of pressure vessel neutron flux results using MCNP program [C ] . The 11th Academic Conference of Reactor Numerical Calculation and Particle Transport and 2006 Reactor Physics Conference , 2006 : 666 - 675 .

U.S. Nuclear Regulatory Commission. Regulatory guide 1.190. calculational and dosimetry methods for determining pressure vessel neutron f1uence [R ] . 2001 .

Wagner J C . Monte Carlo transport calculations and analysis for reactor pressure vessel neutron fluence [D ] . The Pennsylvania State University , 1994 .

Los Alamos National Laboratory. MCNP4C: Monte Carlo N-particle transport code system [R ] . 2001 .

刘同先 . MCNP在中子输运问题计算中的影响因素分析 [D ] . 哈尔滨 : 哈尔滨工程大学 , 2007 .

LIU Tongxian . The analysis of influencing factors in neutron transport problem calculation using MCNP [D ] . Harbin : Harbin Engineering University , 2007 .

浏览量

下载量

CSCD

文章被引用时，请邮件提醒。

提交

工具集

关联资源

球床式高温气冷堆物理热工计算程序NECP-Panda中子学计算模块研制

轻量化通用活化-燃耗分析程序LightAB开发与验证

α粒子测量中的参数计算方法研究

微型反应堆高速撞击下核临界安全的初步分析

基于医用质子直线注入器的超高剂量率细胞辐照实验平台的设计