自动化与仪表2024,Vol.39Issue(9) :6-9,14.DOI:10.19557/j.cnki.1001-9944.2024.09.002

大型池式钠冷快堆热功率的计算和不确定度分析

Thermal Power Calculation and Uncertainty Analysis of Large Pool Sodium-cooled Fast Reactor

郭忠孝 杨军 喻宏 刘一哲
自动化与仪表2024,Vol.39Issue(9) :6-9,14.DOI:10.19557/j.cnki.1001-9944.2024.09.002

大型池式钠冷快堆热功率的计算和不确定度分析

Thermal Power Calculation and Uncertainty Analysis of Large Pool Sodium-cooled Fast Reactor

郭忠孝 1杨军 1喻宏 1刘一哲1
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作者信息

  • 1. 中国原子能科学研究院,北京 102413
  • 折叠

摘要

反应堆的核功率无法直接测量,通过测量中子注量率的大小来表征核功率的大小,因此核电厂通常采用热功率刻度反应堆的核功率.池式钠冷快堆冷却剂系统采用钠-钠-水3个回路的布置形式,与压水堆存在较大差异,由于系统配置的不同,热功率的计算方法与压水堆也存在一定差异.该文分析了大型池式钠冷快堆热功率的计算和不确定度分析方法,用于反应堆核功率测量仪表的标定.计算结果表明,对于大型池式钠冷快堆,热功率计算的不确定度在事故分析初始功率的保守假设之内.堆芯热功率的计算结果主要取决于蒸汽发生器的功率计算,其余各项对最终计算结果的影响小于1%.

Abstract

Reactor nuclear power cannot be measured directly,and it can be represented by the value of the neutron fluence rate.Therefore,thermal power is adopted to calibrate reactor nuclear power in nuclear power plants.The coolant system of pool sodium-cooled fast reactor consists of three circuits of sodium-sodium-water,which is quite dif-ferent from that of pressurized water reactor(PWR).Due to the different configuration of the system,the calculation method of thermal power is also different from that of PWR.In this paper,the calculation method and uncertainty analysis of thermal power in large pool sodium-cooled fast reactor is analyzed,which is used to calibrate the nuclear power measuring instrument of reactor.The results show that for large pool sodium-cooled fast reactor,the uncertainty of thermal power calculation is within the conservative assumption of the initial power of accident analysis,the result of thermal power of core mainly depends on the power of steam generator,and the influence of other factors on the final calculation is less than 1%.

关键词

钠冷快堆/热功率/不确定度

Key words

sodium cooled fast reactor/thermal power/uncertainty

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出版年

2024
自动化与仪表
天津市工业自动化仪表研究所 天津市自动化学会

自动化与仪表

CSTPCD
影响因子:0.548
ISSN:1001-9944
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