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压水堆核电站氚排放源项计算模型参数灵敏度分析 被引量:2

Sensitivity Analysis for Calculation Model Parameters of Tritium Releases Source for PWR
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摘要 氚是核电站运行过程中向环境中排放较大的放射性核素之一,控制核设施中氚的产生和排放量越来越引起人们的重视。本文通过分析核电站产生氚的主要途径,建立了5种产氚途径的7个计算模型,并对计算模型中重要参数的灵敏度进行了分析。结果表明:在计算氚的产生量时,参数的灵敏度依次是~7Li所占百分比、等效满功率天数、初始锂浓度、氚从可燃毒物棒中释放到主冷却剂中份额、氚从燃料释放到冷却剂中份额;~7Li所占百分比对氚的产生量特别灵敏,等效满功率天数对所有途径的产氚量都有影响。 Tritium is the large amount of radionuclide released from nuclear power plant under normal operation. It has attracted more and more attentions to control tritium emissions. By analyzing tritium release pathways of primary loop, seven computational model of five release pathways were established, and sensitivity to most important parameters of models were analysised The results show: the sensitivity of model parameters followed by the percentage of 7Li, effective full power days (EEPD), initial concentration of lithium, tritium release fraction from the combustible poison rods, tritium release fraction from the fuel rods. The percentage of 7Li was highly sensitive to tritium production, EEPD had an impact on all tritium release pathways.
作者 乔亚华 叶远虑 王亮 何亮 余少青 王昆鹏 刘福东 陈鲁 QIAO Ya-hua, YE Yuan-lv, WANG Liang, HE Liang, YU Shao-qing, WANG Kun-peng, LIU Fu-dong, CHEN Lu(Nuclear and Radiation Safety Center, Ministryof Environmental Protection of the People's Republic of China, Beijing 100082, Chin)
出处 《核科学与工程》 CAS CSCD 北大核心 2018年第1期107-113,共7页 Nuclear Science and Engineering
基金 科技部重大专项CAP1400安全评审技术及独立验证试验(2013ZX06002001)
关键词 压水堆 排放源项 灵敏度分析 Tritium Pressurized waterreactor Releases source Sensitivity analysis
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  • 1HU Yongming, LIU Zhihong, SHI Xiuan. De-velopment and verification of quick and precise core physics analysis code[C]//PHYSOR 2010- International Conference on the Physics of Reac- tors. Pittsburgh ANS, 2010.
  • 2刘志宏,胡永明,石秀安.秦山二期核电站多循环换料设计优化研究[C]//第十二届反应堆数值计算与粒子输运学术会议.合肥:[出版者不详],2008.
  • 3赵晶,刘志宏,胡永明.含IFBA可燃毒物组件物理特性研究[C]//第十三届反应堆数值计算与粒子输运学术会议.西安.[出版者不详],2010.
  • 4环境保护部和国家质量监督检验检疫总局.GB6249—2011核动力厂环境辐射防护规定[S].北京:中国环境科学出版社,2011.
  • 5Westinghouse Electric Company LLC. AP1000design control document, Revision 19[R]. USA:Westinghouse Electric Company LLC, 2011.
  • 6上海核工程研究设计院.主回路H-3计算报吿[R].上海:上海核工程研究设计院,2011.
  • 7American Nuclear Society. ANSI/ANS 55. 6—1993 Liquid radioactive waste system for lightwater reactor plants[S]. USA: American Nucle-ar Society, 1993.
  • 8IAEA. Management of waste containing tritiumand carbon-14, TRS 421-2004[R]. Vienna:IAEA, 2004.
  • 9NRC. Calculation of releases of radioactive mate-rials in gaseous and liquid effluents from pressur-ized water reactors PWR-GALE code, NUREG-0017 Rev. 1[R]. USA: NRC, 1985.
  • 10石秀安,刘志宏,胡永明.含有可燃毒物的压水堆核电站堆芯装料设计优化研究[J].核科学与工程,2008,28(2):138-146. 被引量:3

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