J. R. Wang, H. T. Lin, Y. Tseng, W. Y. Li, H. C. Chen, S. W. Chen, C. Shih
{"title":"青山核电站乏燃料池TRACE/FRAPTRAN模型的建立与分析","authors":"J. R. Wang, H. T. Lin, Y. Tseng, W. Y. Li, H. C. Chen, S. W. Chen, C. Shih","doi":"10.5281/ZENODO.1124612","DOIUrl":null,"url":null,"abstract":"TRACE is developed by U.S. NRC for the nuclear \npower plants (NPPs) safety analysis. We focus on the establishment \nand application of TRACE/FRAPTRAN/SNAP models for Chinshan \nNPP (BWR/4) spent fuel pool in this research. The geometry is 12.17 \nm × 7.87 m × 11.61 m for the spent fuel pool. In this study, there are \nthree TRACE/SNAP models: one-channel, two-channel, and \nmulti-channel TRACE/SNAP model. Additionally, the cooling system \nfailure of the spent fuel pool was simulated and analyzed by using the \nabove models. According to the analysis results, the peak cladding \ntemperature response was more accurate in the multi-channel \nTRACE/SNAP model. The results depicted that the uncovered of the \nfuels occurred at 2.7 day after the cooling system failed. In order to \nestimate the detailed fuel rods performance, FRAPTRAN code was \nused in this research. According to the results of FRAPTRAN, the \nhighest cladding temperature located on the node 21 of the fuel rod \n(the highest node at node 23) and the cladding burst roughly after 3.7 \nday.","PeriodicalId":23701,"journal":{"name":"World Academy of Science, Engineering and Technology, International Journal of Chemical, Molecular, Nuclear, Materials and Metallurgical Engineering","volume":"35 1","pages":"704-710"},"PeriodicalIF":0.0000,"publicationDate":"2016-04-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"The Model Establishment and Analysis of TRACE/FRAPTRAN for Chinshan Nuclear Power Plant Spent Fuel Pool\",\"authors\":\"J. R. Wang, H. T. Lin, Y. Tseng, W. Y. Li, H. C. Chen, S. W. Chen, C. Shih\",\"doi\":\"10.5281/ZENODO.1124612\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"TRACE is developed by U.S. NRC for the nuclear \\npower plants (NPPs) safety analysis. We focus on the establishment \\nand application of TRACE/FRAPTRAN/SNAP models for Chinshan \\nNPP (BWR/4) spent fuel pool in this research. The geometry is 12.17 \\nm × 7.87 m × 11.61 m for the spent fuel pool. In this study, there are \\nthree TRACE/SNAP models: one-channel, two-channel, and \\nmulti-channel TRACE/SNAP model. Additionally, the cooling system \\nfailure of the spent fuel pool was simulated and analyzed by using the \\nabove models. According to the analysis results, the peak cladding \\ntemperature response was more accurate in the multi-channel \\nTRACE/SNAP model. The results depicted that the uncovered of the \\nfuels occurred at 2.7 day after the cooling system failed. In order to \\nestimate the detailed fuel rods performance, FRAPTRAN code was \\nused in this research. According to the results of FRAPTRAN, the \\nhighest cladding temperature located on the node 21 of the fuel rod \\n(the highest node at node 23) and the cladding burst roughly after 3.7 \\nday.\",\"PeriodicalId\":23701,\"journal\":{\"name\":\"World Academy of Science, Engineering and Technology, International Journal of Chemical, Molecular, Nuclear, Materials and Metallurgical Engineering\",\"volume\":\"35 1\",\"pages\":\"704-710\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2016-04-06\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"World Academy of Science, Engineering and Technology, International Journal of Chemical, Molecular, Nuclear, Materials and Metallurgical Engineering\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.5281/ZENODO.1124612\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"World Academy of Science, Engineering and Technology, International Journal of Chemical, Molecular, Nuclear, Materials and Metallurgical Engineering","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.5281/ZENODO.1124612","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
The Model Establishment and Analysis of TRACE/FRAPTRAN for Chinshan Nuclear Power Plant Spent Fuel Pool
TRACE is developed by U.S. NRC for the nuclear
power plants (NPPs) safety analysis. We focus on the establishment
and application of TRACE/FRAPTRAN/SNAP models for Chinshan
NPP (BWR/4) spent fuel pool in this research. The geometry is 12.17
m × 7.87 m × 11.61 m for the spent fuel pool. In this study, there are
three TRACE/SNAP models: one-channel, two-channel, and
multi-channel TRACE/SNAP model. Additionally, the cooling system
failure of the spent fuel pool was simulated and analyzed by using the
above models. According to the analysis results, the peak cladding
temperature response was more accurate in the multi-channel
TRACE/SNAP model. The results depicted that the uncovered of the
fuels occurred at 2.7 day after the cooling system failed. In order to
estimate the detailed fuel rods performance, FRAPTRAN code was
used in this research. According to the results of FRAPTRAN, the
highest cladding temperature located on the node 21 of the fuel rod
(the highest node at node 23) and the cladding burst roughly after 3.7
day.
京公网安备 11010802042870号
京ICP备2023020795号-1
分享
求助内容：
应助结果提醒方式：
扫码关注我们
