水冷聚变堆主回路活化产物源项计算分析

李璐; 张竞宇; 郭庆洋; 陈义学

doi:10.11889/j.0253-3219.2016.hjs.39.110603

您当前的位置：

首页 >

文章列表页 >

水冷聚变堆主回路活化产物源项计算分析

核能科学与工程 | 更新时间：2021-05-24

- 水冷聚变堆主回路活化产物源项计算分析
- Calculation and analysis of activation products source term in water-cooled fusion reactor primary circuit
- 核技术 2016年39卷第11期文章编号：110603
- 作者机构：
  
  华北电力大学核科学与工程学院北京 102206
- 作者简介：
  
  [ "李璐,女,1988年出生,2012年毕业于南华大学,现为博士研究生,研究领域为核电厂放射性源项分析", "LI Lu, female, born in 1988, graduated from University of South China in 2012, doctoral student, focusing on the analysis of radioactive source term in the nuclear plant" ]
  张竞宇,E-mail:poptnt@163.com ZHANG Jingyu, E-mail: poptnt@163.com
- 基金信息：
  
  国家自然科学基金(No.11605058);国际热核聚变实验堆计划专项(No.2014GB119000)
- DOI：10.11889/j.0253-3219.2016.hjs.39.110603
  中图分类号： TL929
- 收稿日期：2016-08-11，
  
  修回日期：2016-09-12，
  
  纸质出版日期：2016-11
- 稿件说明：
移动端阅览
李璐, 张竞宇, 郭庆洋, 等. 水冷聚变堆主回路活化产物源项计算分析[J]. 核技术, 2016,39(11):110603

Lu LI, Jingyu ZHANG, Qingyang GUO, et al. Calculation and analysis of activation products source term in water-cooled fusion reactor primary circuit[J]. Nuclear techniques, 2016, 39(11): 110603
李璐, 张竞宇, 郭庆洋, 等. 水冷聚变堆主回路活化产物源项计算分析[J]. 核技术, 2016,39(11):110603 DOI： 10.11889/j.0253-3219.2016.hjs.39.110603.

Lu LI, Jingyu ZHANG, Qingyang GUO, et al. Calculation and analysis of activation products source term in water-cooled fusion reactor primary circuit[J]. Nuclear techniques, 2016, 39(11): 110603 DOI： 10.11889/j.0253-3219.2016.hjs.39.110603.

摘要

水冷聚变堆中结构材料活化腐蚀产物和冷却剂活化产物是正常运行工况下的最主要放射性来源，也是反应堆运行及维护过程中工作人员辐照剂量的直接来源。本文使用CATE V2.1程序对国际热核聚变实验堆（International Thermonuclear Experimental Reactor，ITER）LIM-OBB（Limiter-Out-Board Baffle）冷却回路的活化腐蚀产物和水活化产物进行模拟计算，并根据CATE模拟得到的放射性活度通过点核积分程序分别计算正常运行1.2 a及停堆15 d的剂量率。计算结果表明，反应堆运行期间冷却剂活化产物比活度和剂量率远大于结构材料活化腐蚀产物，而停堆后冷却剂活化产物迅速衰变完，结构材料的活化腐蚀产物成为比活度和剂量率的主要来源。

Abstract

Background

Activated corrosion products (ACPs) from structure materials and coolant activation products are the dominant radiation hazard in water-cooled fusion reactor under normal operation conditions

and directly determine the occupational radiation exposure (ORE) during operation and maintenance.

Purpose

The aim is to quantitatively analysis source term of activation products in International Thermonuclear Experimental Reactor (ITER).

Methods

CATE V2.1 is used to simulate the ACPs from structure materials and coolant activation products in the ITER blanket circuit

and then the dose rate of the LIM-OBB (Limiter-Out-Bboard Baffle) cooling loop operating for 1.2 a

and 15 d after shutdown is calculated by point kernel code ARShield.

Results & Conclusion

Under operation conditions

the specific activity and dose rate of the coolant activation products are much higher than those of ACPs from structure material

while after shutdown

the coolant activation products decay out rapidly

and the ACPs from structure material become the main contributor to specific activity and dose rate.

关键词

Keywords

references

刘原中 . 轻水堆一迥路中放射性核素浓度的计算方法及计算机程序 . 辐射防护 , 1986 . 6 409 - 424 . http://www.cnki.com.cn/Article/CJFDTOTAL-FSFH198606000.htm .

Yuanzhong LIU . A method and computer code for calculating radionuclide concentration in primary coolant circuit of LWRs . Radiation Protection , 1986 . 6 409 - 424 . http://www.cnki.com.cn/Article/CJFDTOTAL-FSFH198606000.htm .

M Rafique , N M Mirza , S M Mirza , . Review of computer codes for modeling corrosion product transport and activity build-up in light water reactors . Nukleonika , 2010 . 55 ( 3 ): 263 - 269 . http://cn.bing.com/academic/profile?id=1497935989&encoded=0&v=paper_preview&mkt=zh-cn .

Pace L Di , F Dacquait , P Schindler , . Development of the PACTITER code and its application to safety analyses of ITER primary cooling water system . Fusion Engineering and Design , 2007 . 82 ( 3 ): 237 - 247 . DOI: 10.1016/j.fusengdes.2006.11.002 http://doi.org/10.1016/j.fusengdes.2006.11.002 .

P J Karditsas . Activation product transport using TRACT:ORE estimation of an ITER cooling loop . Fusion Engineering and Design , 1999 . 45 ( 2 ): 169 - 185 . DOI: 10.1016/S0920-3796(99)00004-6 http://doi.org/10.1016/S0920-3796(99)00004-6 .

L Li , J Y Zhang , W Song , . CATE:a code for activated corrosion products evaluation of water-cooled fusion reactor . Fusion Engineering and Design , 2015 . 100 340 - 344 . DOI: 10.1016/j.fusengdes.2015.06.193 http://doi.org/10.1016/j.fusengdes.2015.06.193 .

J Y Zhang , L Li , S X He , . Development of a three-zone transport model for activated corrosion products analysis of tokamak cooling water system . Fusion Engineering and Design , 2016 . 109-111 407 - 410 . DOI: 10.7538/yzk.2015.49.S0.0068 http://doi.org/10.7538/yzk.2015.49.S0.0068 .

R A Forrest . The european activation file:EAF-2007 decay data library , : UK Euratom/Ukaea Fusion Association , 2007 . 8 - 40 .

R A Forrest , J Kopecky , J C Sublet . The european activation file:EAF-2007 neutron-induced cross section library , : UK Euratom/Ukaea Fusion Association , 2007 . 19 - 21 .

EDA ITER . Documentation series No.24:ITER technical basis , : Vienna International Atomic Energy Agency, IAEA , 2002 . 445 - 446 .

J Valentin . The 2007 recommendations of the international commission on radiological protection , : Oxford, UK Elsevier , 2007 . 1 - 332 .

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

基于CODAC的ITER电流引线测控系统