核电厂氧化运行期间冷却剂中<sup>58</sup>Co活度浓度的现场监测

夏三强; 刘立业; 曹勤剑; 胡凌; 李刚; 郑明贵; 胡智彬

doi:10.11889/j.0253-3219.2018.hjs.41.120603

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核电厂氧化运行期间冷却剂中⁵⁸Co活度浓度的现场监测

核能科学与工程 | 更新时间：2021-05-19

- 核电厂氧化运行期间冷却剂中⁵⁸Co活度浓度的现场监测
- On-site monitoring the activity concentration of nuclide ⁵⁸Co in coolant during PWR oxygenation shutdown
- 核技术 2018年41卷第12期文章编号：120603
- 作者机构：
  
  1.中国辐射防护研究院太原 030006
  2.福建福清核电有限公司福清 350300
  3.中国地质大学武汉 430074
- 作者简介：
  
  [ "夏三强, 男, 1988年出生, 2015年于中国辐射防护研究院获硕士学位, 助理研究员, 研究领域为辐射防护与环境保护", "XIA Sanqiang, male, born in 1988, graduated from China Institute for Radiation Protection with a master's degree in 2015, research assistant professor, engaged in radiation protection and environmental protection" ]
  刘立业, E-mail:liuliye@cirp.org.cn LIU liye, E-mail:liuliye@cirp.org.cn
- 基金信息：
  
  国家自然科学基金(11605162)
- DOI：10.11889/j.0253-3219.2018.hjs.41.120603
  中图分类号： TL814
- 收稿日期：2018-08-21，
  
  修回日期：2018-10-23，
  
  纸质出版日期：2018-12-10
- 稿件说明：
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夏三强, 刘立业, 曹勤剑, 等. 核电厂氧化运行期间冷却剂中⁵⁸Co活度浓度的现场监测[J]. 核技术, 2018,41(12):120603

Sanqiang XIA, Liye LIU, Qinjian CAO, et al. On-site monitoring the activity concentration of nuclide ⁵⁸Co in coolant during PWR oxygenation shutdown[J]. Nuclear techniques, 2018, 41(12): 120603
夏三强, 刘立业, 曹勤剑, 等. 核电厂氧化运行期间冷却剂中⁵⁸Co活度浓度的现场监测[J]. 核技术, 2018,41(12):120603 DOI： 10.11889/j.0253-3219.2018.hjs.41.120603.

Sanqiang XIA, Liye LIU, Qinjian CAO, et al. On-site monitoring the activity concentration of nuclide ⁵⁸Co in coolant during PWR oxygenation shutdown[J]. Nuclear techniques, 2018, 41(12): 120603 DOI： 10.11889/j.0253-3219.2018.hjs.41.120603.

摘要

氧化运行期间，通过化学连续取样测定冷却剂中

Co的活度浓度峰值和达到氧化运行结束条件的时间（活度浓度

25 GBq·t

-1

）时，会产生大量放射性废液。为减少取样产生的放射性废液，设计利用高纯锗就地γ测量系统在管道外进行γ谱测量，获得

Co特征峰净计数率随停堆时间实时变化数据，藉此预判

Co活度浓度达到峰值时间和氧化运行结束时间，然后进行取样分析。在某核电站氧化运行期间，利用系统进行γ谱连续测量，判断

Co活度浓度峰值时间是停堆后33 h 39 min（±10 min），氧化运行结束时间是停堆后57 h（±10min）；连续取样数据测量判断

Co活度浓度峰值时间是停堆后33 h 34 min，氧化运行结束时间是停堆后57 h 9 min。两种方法判断达到峰值和氧化运行结束时间误差都在10 min以内。

Abstract

Background

During the oxidation operation of a reactor

the max active concentration of

Co in the coolant and the time to the end of the oxidation operation (activity concentration

25 GBq·t

-1

) are compulsory. The current chemical sampling method produces large amounts of radioactive waste liquid.

Purpose

This study aims to reduce the current radioactive waste liquid by establishing an external γ spectrum monitoring system.

Methods

The HPGe γ measurement system is used to measure the γ spectrum of the coolant outside the pipeline. The net count rates of the

Co characteristic peak varition with time were obtained after reactor shutdown. These data can be used to predict the time to reach the maximum active concentration of

Co in the coolant and the time to reach the end of the oxidation operation

and then performed a sample analysis.

Results

During the oxidation operation of a nuclear power plant

this monitoring system was used to continuously measure the γ spectrum outside the pipeline. The time of the maximum activity concentration of

Co was predicted to be 33 h and 39 min after shutdown

and the oxidation operation end time predicted to be 57 h after shutdown. By continuously coolant sampling data

the time of the maximum activity concentration of

Co was 33 h and 34 min after shutdown

and the oxidation operation end time was 57 h and 9 min after shutdown. Two time errors are in normal range (less than 10 min).

Conclusions

The external monitoring method can reduce the sampling frequency significantly and reduce the amount of radioactive waste generated by sampling analysis.

关键词

Keywords

references

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核电厂氧化运行期间冷却剂中58Co活度浓度的现场监测

On-site monitoring the activity concentration of nuclide 58Co in coolant during PWR oxygenation shutdown

DOI：10.11889/j.0253-3219.2018.hjs.41.120603

摘要

Abstract

关键词

Keywords

references

核电厂氧化运行期间冷却剂中⁵⁸Co活度浓度的现场监测

On-site monitoring the activity concentration of nuclide ⁵⁸Co in coolant during PWR oxygenation shutdown