“华龙一号”SGTR事故源项分析方法研究
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摘要
在充分借鉴已有的工程实践和安全审评经验、参考核电发达国家成熟的分析方法和最新研究成果,并考虑"华龙一号"核电厂实际设计特点及事故应对策略的基础上,提出一套基于事故并发碘尖峰模型的蒸汽发生器传热管破裂事故源项分析方法,并采用该方法分析了"华龙一号"核电厂蒸汽发生器传热管破裂事故源项。分析结果表明,采用该方法计算得到的事故源项,其放射性后果满足GB 6249(2011)规定的事故放射性后果接受准则。该方法与国标对三类事故放射性后果接受准则是相配套的,并避免了蒸汽发生器传热管破裂事故源项分析采用与其他事故源项分析均不同的重要输入参数。该方法可用于"华龙一号"其他三类事故源项分析,同时为国内设计基准事故源项分析相关导则、法规的实施提供参考。
A SGTR accident source term analysis methodology based on accident initiated iodine spike model is proposed for HPR1000 nuclear power plant. Existing engineering practice and safety review experiences are learned,and well-understood methodologies in advanced nuclear power countries and latest R&D results are referred in this methodology.Specific designs and accident management strategies of HPR1000 are also considered. SGTR accident source term of HPR1000 is analyzed by this methodology and the results show that radiological consequence of this accident meets the dose acceptance criteria provided in GB-6249(2011).This methodology is compatible with the dose acceptance criteria for category Ⅲ accident provided in GB-6249(2011),and avoids the source term analysis of steam generator heat transfer tube rupture accident to adopt important input parametersdifferent from other accident source term analyses. This methodology can also be applied to other category III accident source term analyses and provide references for the implementation of related guides or regulations for domestic design basis accident source term analysis.
A SGTR accident source term analysis methodology based on accident initiated iodine spike model is proposed for HPR1000 nuclear power plant. Existing engineering practice and safety review experiences are learned,and well-understood methodologies in advanced nuclear power countries and latest R&D results are referred in this methodology.Specific designs and accident management strategies of HPR1000 are also considered. SGTR accident source term of HPR1000 is analyzed by this methodology and the results show that radiological consequence of this accident meets the dose acceptance criteria provided in GB-6249(2011).This methodology is compatible with the dose acceptance criteria for category Ⅲ accident provided in GB-6249(2011),and avoids the source term analysis of steam generator heat transfer tube rupture accident to adopt important input parametersdifferent from other accident source term analyses. This methodology can also be applied to other category III accident source term analyses and provide references for the implementation of related guides or regulations for domestic design basis accident source term analysis.
引文
[1]环境保护部、国家质量监督检验检疫总局.核动力厂环境辐射防护规定:GB 6249-2011[S].北京:中国环境科学出版社,2011.
[2]U.S.NUCLEAR REGULATORY COMMISSION.Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,Regulatory Guide1.183[R],USA:Nuclear Regulatory Commission,2000.
[3]EDF AND FRAMATOME.Design and Construction Rules for System Design of 900 MWe PWR Nuclear Power Plants,RCC-P[R],EDF and FRAMATOME,1991.
[4]CLEMENT B,and SIMONDI-TEISSEIRE B.STEM:An IRSN project on source term evaluation and mitigation,2010 ANS Annual Meeting[C],Las Vegas,NV,U.S,2010.
[5]陈洋,丁四中,上官志洪.AP1000和CPR1000核电机组SGTR事故释放源项比较分析[J],辐射防护,2015,31(3):129-134.
[6]WESTINGHOUSE.Iodine and Cesium Spiking Source Terms for Accident Analyses,WACP-9964[R],Westinghouse Nuclear Technology Division,1981.
[7]中华人民共和国环境保护部.核安全与放射性污染防治“十二五”规划及2020远景目标[R].北京:环境保护部,2012.
[2]U.S.NUCLEAR REGULATORY COMMISSION.Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,Regulatory Guide1.183[R],USA:Nuclear Regulatory Commission,2000.
[3]EDF AND FRAMATOME.Design and Construction Rules for System Design of 900 MWe PWR Nuclear Power Plants,RCC-P[R],EDF and FRAMATOME,1991.
[4]CLEMENT B,and SIMONDI-TEISSEIRE B.STEM:An IRSN project on source term evaluation and mitigation,2010 ANS Annual Meeting[C],Las Vegas,NV,U.S,2010.
[5]陈洋,丁四中,上官志洪.AP1000和CPR1000核电机组SGTR事故释放源项比较分析[J],辐射防护,2015,31(3):129-134.
[6]WESTINGHOUSE.Iodine and Cesium Spiking Source Terms for Accident Analyses,WACP-9964[R],Westinghouse Nuclear Technology Division,1981.
[7]中华人民共和国环境保护部.核安全与放射性污染防治“十二五”规划及2020远景目标[R].北京:环境保护部,2012.