{"title":"狭缝出口附近的临界流断源项","authors":"Weiguo Gu , Yuxiang He , Dezhong Wang","doi":"10.1016/j.pnucene.2025.105878","DOIUrl":null,"url":null,"abstract":"<div><div>LBB (Leak-before-break) radioactive aerosol monitor in the nuclear power plant requires knowledge of the source term to build the relationship between monitored radiation activity and the leak flow rate. The leak flow rate could be used to evaluate the risk of LOCA (Loss of Coolant Accident). The source term, including initial diameter distribution, and initial concentration, comes from the break of the liquid phase in the critical flow existing in the crack. The relationship between the source term and the critical flow is complicated and requires dimensional analysis to be built. Experiments of water and R134a under lower stagnant pressure and lower stagnant temperature than the primary loop are conducted to measure the critical flow pattern, spray shape, and droplet diameter distribution near the outlet of the slit (simplified crack). Non-dimensional numbers based on the outlet physical variables are calculated by TFM-DEM (Two-fluid Model-Delayed Equilibrium Model), and the relation between diameter distribution coefficients and non-dimensional numbers is built by regression analysis. It is found that the critical flow patterns are similar and have no relationship with the break, while the spray shapes could be split into three groups, and the break relationships are different among them. Linear discriminant analysis is used to classify different spray shapes and different breaking modes. The relations are effective as long as the range of major non-dimensional numbers related to the breaking process covers those of actual industrial cases. The initial concentration is researched using random sampling and regression analysis so that it can be calculated using the gas phase volume fraction at the outlet. The source term equations, non-dimensional analysis, and random sampling process would be of great help in the development of more accurate model for the source term of LBB aerosol monitor with more complete source term measurement results in the future.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"188 ","pages":"Article 105878"},"PeriodicalIF":3.2000,"publicationDate":"2025-06-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Critical flow break source term near the outlet of a slit\",\"authors\":\"Weiguo Gu , Yuxiang He , Dezhong Wang\",\"doi\":\"10.1016/j.pnucene.2025.105878\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>LBB (Leak-before-break) radioactive aerosol monitor in the nuclear power plant requires knowledge of the source term to build the relationship between monitored radiation activity and the leak flow rate. The leak flow rate could be used to evaluate the risk of LOCA (Loss of Coolant Accident). The source term, including initial diameter distribution, and initial concentration, comes from the break of the liquid phase in the critical flow existing in the crack. The relationship between the source term and the critical flow is complicated and requires dimensional analysis to be built. Experiments of water and R134a under lower stagnant pressure and lower stagnant temperature than the primary loop are conducted to measure the critical flow pattern, spray shape, and droplet diameter distribution near the outlet of the slit (simplified crack). Non-dimensional numbers based on the outlet physical variables are calculated by TFM-DEM (Two-fluid Model-Delayed Equilibrium Model), and the relation between diameter distribution coefficients and non-dimensional numbers is built by regression analysis. It is found that the critical flow patterns are similar and have no relationship with the break, while the spray shapes could be split into three groups, and the break relationships are different among them. Linear discriminant analysis is used to classify different spray shapes and different breaking modes. The relations are effective as long as the range of major non-dimensional numbers related to the breaking process covers those of actual industrial cases. The initial concentration is researched using random sampling and regression analysis so that it can be calculated using the gas phase volume fraction at the outlet. The source term equations, non-dimensional analysis, and random sampling process would be of great help in the development of more accurate model for the source term of LBB aerosol monitor with more complete source term measurement results in the future.</div></div>\",\"PeriodicalId\":20617,\"journal\":{\"name\":\"Progress in Nuclear Energy\",\"volume\":\"188 \",\"pages\":\"Article 105878\"},\"PeriodicalIF\":3.2000,\"publicationDate\":\"2025-06-24\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Progress in Nuclear Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0149197025002768\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197025002768","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Critical flow break source term near the outlet of a slit
LBB (Leak-before-break) radioactive aerosol monitor in the nuclear power plant requires knowledge of the source term to build the relationship between monitored radiation activity and the leak flow rate. The leak flow rate could be used to evaluate the risk of LOCA (Loss of Coolant Accident). The source term, including initial diameter distribution, and initial concentration, comes from the break of the liquid phase in the critical flow existing in the crack. The relationship between the source term and the critical flow is complicated and requires dimensional analysis to be built. Experiments of water and R134a under lower stagnant pressure and lower stagnant temperature than the primary loop are conducted to measure the critical flow pattern, spray shape, and droplet diameter distribution near the outlet of the slit (simplified crack). Non-dimensional numbers based on the outlet physical variables are calculated by TFM-DEM (Two-fluid Model-Delayed Equilibrium Model), and the relation between diameter distribution coefficients and non-dimensional numbers is built by regression analysis. It is found that the critical flow patterns are similar and have no relationship with the break, while the spray shapes could be split into three groups, and the break relationships are different among them. Linear discriminant analysis is used to classify different spray shapes and different breaking modes. The relations are effective as long as the range of major non-dimensional numbers related to the breaking process covers those of actual industrial cases. The initial concentration is researched using random sampling and regression analysis so that it can be calculated using the gas phase volume fraction at the outlet. The source term equations, non-dimensional analysis, and random sampling process would be of great help in the development of more accurate model for the source term of LBB aerosol monitor with more complete source term measurement results in the future.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.