期刊文献+

核电厂氢气浓度监测系统设计

Design of Hydrogen Concentration Analyzer in Nuclear Power Plant
下载PDF
导出
摘要 针对核电厂安全壳内氢气浓度泄漏的监测需求,基于钯合金氢敏薄膜原理设计了核电厂氢气浓度监测系统。根据钯合金氢气传感器随环境温度、环境压力的变化特性,开发了氢气传感器温度、压力补偿算法;结合安全壳模拟容器内的应用场景,进行了测量系统的总体设计,并对设备性能进行了测试分析。研究结果表明,在0%~20%的浓度范围内,低温120℃及高温150℃条件下,氢气浓度监测系统的最大示值误差分别为0.5%FS及-0.78%FS,均低于±2.5%FS,响应时间均为17 s,小于40 s;高温150℃时测试结果显示,系统检测精度优于0.02%;标准浓度为3%及10%的稳定性测试中,最大示值误差为-1.3%FS,具有良好的长期稳定性。该氢气浓度监测系统性能技术指标满足设计要求,可为核电厂安全壳氢气泄漏监测提供有效的解决方案。 In order to monitor the leakage of hydrogen concentration in the containment of nuclear power plant,a monitoring system for hydrogen concentration in nuclear power plant was designed based on the principle of palladium alloy hydrogen sensitive film.According to the variation characteristics of palladium alloy hydrogen sensor with ambient temperature and pressure,the temperature and pressure compensation algorithm of hydrogen sensor was developed.Combined with the application scenario in the containment simulation vessel,the overall design of the measurement system is carried out,and the performance of the equipment is tested and analyzed.The results show that in the concentration range of 0%~20%,under the conditions of 120℃and 150℃,the maximum error of hydrogen concentration monitoring system is0.5%FS and-0.78%FS,respectively,which are lower than±2.5%FS.The response time is 17 s and less than 40 s.When the temperature is 150℃,the test results show that the detection accuracy of the system is better than 0.02%.The maximum value error in the stability test of the standard concentration of3%and 10%is-1.3%FS,which has good long-term stability.The performance and technical indexes of the hydrogen concentration monitoring system meet the design requirements.And it can provide an effective solution for hydrogen leakage monitoring of nuclear containment.
作者 许雪锋 汪献忠 赫树开 王三霞 曾晓哲 王幸辉 侯新梅 XU Xue-feng;WANG Xian-zhong;HE Shu-kai;WANG San-xia;ZENG Xiao-zhe;WANG Xing-hui;HOU Xin-mei(Henan Relations Co.,Ltd,Zhengzhou 450001,China;School of Physical Engineering,Zhengzhou University,Zhengzhou 450001,China)
出处 《核电子学与探测技术》 CAS 北大核心 2023年第2期348-354,共7页 Nuclear Electronics & Detection Technology
基金 国家重点研发计划项目(2020YFB2008600)资助。
关键词 钯合金薄膜 温压补偿算法 核电厂 安全壳 氢气浓度监测系统 palladium alloy film temperature and pressure compensation algorithm nuclear power plant containment hydrogen concentration monitoring system
  • 相关文献

参考文献8

二级参考文献51

  • 1陈松,刘鑫,史国宝,朱鑫官,蔡剑平.严重事故下安全壳内环境条件计算分析[J].核动力工程,2006,27(z1):13-17. 被引量:13
  • 2陆如山,韩秀霞.有关切尔诺贝利核事故影响健康的报告[J].国外医学情报,2006,27(6):2-3. 被引量:2
  • 3国家核安全局.HAF102核动力厂设计安全规定[s].2004.
  • 4CLEMENT B, PETIT M,et al. In-vessel and ex-vessel hydrogensources[ R]. Report NEA/CSNI R,15,2001.
  • 5International Atomic Energy Agency( IAEA) . Mitigation ofhydrogen hazards in water cooled power reactors [ R ].Report IAEA - TECDOG -1196,2001.
  • 6DENG J,CAO X W. A study on evaluating a passive autocatalyticrecombiner PAR-system in the PWR large-dry containment[J ]. Nuclear Engineering and Design, 2008, 238: 2554-2560.
  • 7International Atomic Energy Agency ( IAEA ) . Defence indepth in nuclear safety [ R ]. INSAG - 10 - Safety SeriesNo. 75,1996.
  • 8National Nuclear Safety Administration of China( NNSA).Technology policy about several important safety problemsin designing a new nuclear power plant [ R]. Nuclear SafetyNotice ,2002.
  • 9National Nuclear Safety Administration of China( NNSA).Safety of nuclear power plants : design [ R ]. Safety SeriesHAF 102,2005.
  • 10International Atomic Energy Agency (IAEA). Mitigation ofHydrogen Hazards in Severe Accidents in Nuclear PowerPlants [ R]. IAEA - TECDOC - 1661,2011.

共引文献25

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部