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COSINE软件临界后传热保守模型开发与确认

Development and verification of Post-CHF Heat Transfer ConservativeModel in COSINE

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【作者】 孔晓宁陈俊孙琼华杨燕华

【Author】 Xiaoning KONG;Jun CHEN;Qionghua Sun;Yanhua YANG;State Power Investment Central Research Institute;National Energy Key Laboratory of Nuclear Power Software;Shanghai Jiao Tong University;

【机构】 国家电投集团科学技术研究院有限公司国家能源核电软件重点实验室上海交通大学核能科学与工程学院

【摘要】 失水事故保守分析软件(cosCSLOCA)是COSINE软件包中热工水力分析程序之一。其采用NRC 10CFR50.46附录K推荐的保守模型,适用于核电厂的失水事故分析。临界后换热模型是失水事故保守分析软件的重要模型,也是预测失水事故中包壳峰值温度的关键模型。本文介绍了cosCSLOCA软件中临界后换热模型在过渡沸腾和模态沸腾的代码开发中使用的关系式。此外,采用美国橡树岭国家实验室的ORNL-THTF试验评估失水事故保守分析软件的临界后传热模型,并将cosCSLOCA程序的计算结果和relap5计算结果及实验数据进行了比较。结果表明,两个程序的计算结果与实验结果具有相同的趋势,用cosCSLOCA计算的包壳峰值温度高于relap5计算结果和实验结果,从而证明了失水事故保守分析软件中临界后传热模型的正确性和保守性。

【Abstract】 cosCSLOCAis a sub-program among the thermal hydraulic design and safety analysis codes in COSINE software package. It is applicable to analyze theloss of coolant accidents(LOCA) in nuclear power plants and use the conservative modelsrecommended in appendix K of NRC 10 CFR50.46. And the post-CHF heat transfer is an important phenomenonto predict the peak cladding temperature during a LOCA.This paper introduces the development process ofpost-CHF heat transfer, andlisted the correlations oftransition boilingand film boiling adopted in cosCSLOCA.In addition, the separate effect experiment ORNL-THTF experiment tests have been used for the verification of the proposed Post-CHF heat transfer models in cosCSLOCA. Comparisons are made between the experimental results, the results calculated by cosCSLOCA and relap5. The results show that the temperatures of the heat structure surface calculated by the two codes had the same trend with experiment, and the calculated cladding temperatures using cosCSLOCA are higher than relap5 and experiment data. Through the separate effect assessments, the conservative and validity of the post-CHF heat transfer model in cosCSLOCA were verified.

【基金】 国家科技重大专项(No.2017ZX06004-002)
  • 【会议录名称】 第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集
  • 【会议名称】第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会
  • 【会议时间】2019-11-06
  • 【会议地点】中国广东惠州
  • 【分类号】TL364.4;TL33
  • 【主办单位】中国核学会核能动力分会反应堆热工流体专业委员会、中核核反应堆热工水力技术重点实验室、核反应堆热工流体青年工作委员会
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