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中广核自主污垢行为分析软件CAMPSIS1.0研发与验证 被引量:1

Development and Verification of CAMPSIS 1.0-A Crud Behavior Analysis Code
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摘要 压水堆污垢行为涉及材料、化学、热工、中子学等多个学科,包含了较为复杂的物理过程,可能引发污垢导致功率偏移(CIPS)、污垢导致局部腐蚀(CILC)等潜在运行风险,也会影响一回路冷却剂及金属表面的放射性剂量。自2018年开始,历时3年中广核开发了自主污垢行为分析软件CAMPSIS1.0,它包含腐蚀释放、水化学、核素活化、污垢沉积等污垢行为模拟所需的核心模型,同时具备了CIPS、CILC风险分析和一回路腐蚀产物活化源项分析的能力。通过实验数据、电厂正常运行和停堆期间的测量数据对软件进行了系统验证。结果表明,CAMPSIS1.0初步具备了在工程上进行污垢行为分析的能力。 The crud behavior in PWRs involves complex physical processes that consist of several subjects including material science, chemistry, thermal hydraulics, neutronics, etc. It could induce CIPS(CRUD induced power shift) and CILC(CRUD induced localized corrosion)phenomena which will not only lead potential risks to plant operation, but also influence the radioactive dose of the moderator and metal surface. Internationally, the US developed code BOA is widely adopted to perform risk analysis of CIPS and CILC, and the PACTOLE or OSCAR code developed in FRANCE is utilized to perform source term analysis of the corrosion products. Since 2018, CGN took three years to develop its own crud behavior code CAMPSIS 1.0. The code contains the core models of corrosion release, water chemistry, nuclide activation and crud deposition which makes CAMPSIS capable to perform risk analysis of CIPS and CILC and source term analysis at the same time. CAMPSIS has been verified against experiment data, measurements in normal operational conditions and shutdown periods. Results showed that CAMPSIS 1.0 is capable to perform crud behavior analysis in engineering-level.
作者 彭思涛 蒙舒祺 张一骏 付鹏涛 洪亮 阮天鸣 周青 张晓茜 赵园 厉井钢 PENG Sitao;MENG Shuqi;ZHANG Yijun;FU Pengtao;HONG Liang;RUAN Tianming;ZHOU Qing;ZHANG Xiaoqian;ZHAO Yuan;LI Jinggang(China Nuclear Power Technology Research Institute,Shenzhen of Guangdong Prov.518026,China)
出处 《核科学与工程》 CAS CSCD 北大核心 2022年第6期1235-1241,共7页 Nuclear Science and Engineering
基金 国家自然科学基金(U20B0211,针对堆芯氧化腐蚀产物材料-热工-中子行为的多物理耦合机理) 国家自然科学基金(52171085,模拟压水堆一回路冷却剂中燃料包壳管表面污垢沉积行为与机理研究)。
关键词 压水堆 燃料污垢 行为分析 运行 源项 PWR Fuel CRUD Behavior analysis Operation Activation
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  • 1朱小明,黄红波,林俊,夏元复,丁亚平,徐雪莲.用XPS分析喷丸处理后800合金在强碱溶液中的腐蚀产物[J].中国腐蚀与防护学报,2004,24(4):213-217. 被引量:5
  • 2B. Stellwag.The mechanism of oxide film formation on austenitic stainless steels in high temperature water[J].Corrosion Science.1998(2)
  • 3S.E. Ziemniak,M. Hanson.Corrosion behavior of 304 stainless steel in high temperature, hydrogenated water[J].Corrosion Science.2002(10)
  • 4P Stefanov,D Stoychev,M Stoycheva,Ts Marinova.XPS and SEM studies of chromium oxide films chemically formed on stainless steel 316 L[J].Materials Chemistry and Physics.2000(2)
  • 5D.R. Diercks,W.J. Shack,J. Muscara.Overview of steam generator tube degradation and integrity issues[J].Nuclear Engineering and Design.1999(1)
  • 6S.J. Green,G. Hetsroni.PWR steam generators[J].International Journal of Multiphase Flow.1995
  • 7韩恩厚,王俭秋,吴欣强,柯伟.核电高温高压水中不锈钢和镍基合金的腐蚀机制[J].金属学报,2010,46(11):1379-1390. 被引量:57
  • 8海正银,王辉,辛长胜,蔡敏,秦博,陈童.加锌对690合金在高温水中形成的氧化膜的影响[J].中国腐蚀与防护学报,2014,34(6):532-536. 被引量:2

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