The Experts below are selected from a list of 12921 Experts worldwide ranked by ideXlab platform
W X Tian - One of the best experts on this subject based on the ideXlab platform.
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thermal Hydraulic Phenomena related to small break locas in ap1000
Progress in Nuclear Energy, 2011Co-Authors: Wei Wang, S Z Qiu, W X TianAbstract:Abstract Since the TMI accident in 1979, a lot of attention in the nuclear engineering field has been drawn to the small break LOCA issue, around which plenty of work has been done both experimentally and theoretically. Subsequent reactor designs have also been greatly influenced. As a Generation III + reactor that received Final Design Approval by U.S. NRC, AP1000 employs a series of passive safety systems to improve its safety. However, the thermal Hydraulic Phenomena related to small break LOCAs in AP1000 have not been fully understood and further studies are still required. This paper investigated the available literature and information on thermal Hydraulic Phenomena that occur during small break LOCAs in AP1000, which included the critical flow, natural circulation, counter-current flow limiting, entrainment, reactor vessel level swell, direct contact condensation and thermal stratification. In particular, the physical Phenomena, theoretical and experimental research conducted in the past few decades, and prediction models as well as their comparison and evaluation for the thermal Hydraulic Phenomena related to the small break LOCAs in AP1000 were concluded.
Wei Wang - One of the best experts on this subject based on the ideXlab platform.
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thermal Hydraulic Phenomena related to small break locas in ap1000
Progress in Nuclear Energy, 2011Co-Authors: Wei Wang, S Z Qiu, W X TianAbstract:Abstract Since the TMI accident in 1979, a lot of attention in the nuclear engineering field has been drawn to the small break LOCA issue, around which plenty of work has been done both experimentally and theoretically. Subsequent reactor designs have also been greatly influenced. As a Generation III + reactor that received Final Design Approval by U.S. NRC, AP1000 employs a series of passive safety systems to improve its safety. However, the thermal Hydraulic Phenomena related to small break LOCAs in AP1000 have not been fully understood and further studies are still required. This paper investigated the available literature and information on thermal Hydraulic Phenomena that occur during small break LOCAs in AP1000, which included the critical flow, natural circulation, counter-current flow limiting, entrainment, reactor vessel level swell, direct contact condensation and thermal stratification. In particular, the physical Phenomena, theoretical and experimental research conducted in the past few decades, and prediction models as well as their comparison and evaluation for the thermal Hydraulic Phenomena related to the small break LOCAs in AP1000 were concluded.
Ming Tao Cui - One of the best experts on this subject based on the ideXlab platform.
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Analyses of ACME integral test results on CAP1400 small-break loss-of-coolant-accident transient
Progress in Nuclear Energy, 2016Co-Authors: Chang Huajian, Fang Fang Fang, Yan Shi, Kai Yang, Ming Tao CuiAbstract:Abstract CAP1400 has been developed as a new passive safety and generation III + reactor based on AP600/1000 technology. Like previous reactors, the small-break loss-of-coolant-accident (SBLOCA) is still one of the most important safety problems that have to be considered before it's widely applications. Although extensive theoretical and experimental results of SBLOCA have been reported in previous studies, the dominant SBLOCA transient mechanisms and the important thermal Hydraulic Phenomena have not been clearly explained, especially in the passive safety system, due to the complexity of the passive safety nuclear reactor geometry coupled with the transient two-phase fluid interactions. In this study, a new constructed thermal Hydraulic integral effect test facility, named as advanced core-cooling mechanism experiment (ACME), which is designed and constructed for supporting CAP1400 safety review, was used to investigate the SBLOCA transient in passive safety plants. 1-inch, 2-inch and 8-inch cold leg breaks and a double-ended direct-vessel-injection (DEDVI) line break were selected as the critical and essential SBLOCA tests. The system pressure, injection flow rate, core level and fluid temperature were considered as the safety related parameters to investigate the system responses to the SBLOCA. In addition, the conditions that affect the SBLOCA chronology were investigated as well. Also, a few important thermal Hydraulic Phenomena observed in the ACME SBLOCA test were reported, and their effects on the transient were analyzed. The dominant SBLOCA transient mechanisms in the passive safety system were presented. This study not only helps to improve the understanding of SBLOCA mechanisms and important thermal Hydraulic Phenomena in passive safety systems, but also sheds some lights on SBLOCA analysis, test facility scaling, safety performance evaluation, code simulation and even the design optimization for the passive safety PWRs.
S Z Qiu - One of the best experts on this subject based on the ideXlab platform.
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thermal Hydraulic Phenomena related to small break locas in ap1000
Progress in Nuclear Energy, 2011Co-Authors: Wei Wang, S Z Qiu, W X TianAbstract:Abstract Since the TMI accident in 1979, a lot of attention in the nuclear engineering field has been drawn to the small break LOCA issue, around which plenty of work has been done both experimentally and theoretically. Subsequent reactor designs have also been greatly influenced. As a Generation III + reactor that received Final Design Approval by U.S. NRC, AP1000 employs a series of passive safety systems to improve its safety. However, the thermal Hydraulic Phenomena related to small break LOCAs in AP1000 have not been fully understood and further studies are still required. This paper investigated the available literature and information on thermal Hydraulic Phenomena that occur during small break LOCAs in AP1000, which included the critical flow, natural circulation, counter-current flow limiting, entrainment, reactor vessel level swell, direct contact condensation and thermal stratification. In particular, the physical Phenomena, theoretical and experimental research conducted in the past few decades, and prediction models as well as their comparison and evaluation for the thermal Hydraulic Phenomena related to the small break LOCAs in AP1000 were concluded.
Yutaka Kukita - One of the best experts on this subject based on the ideXlab platform.
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PWR Small Break Loss-of-Coolant-Accident Experiment at ROSA-V/LSTF with a Combination of Secondary-Side Depressurization and Gravity-Driven Safety Injection
Journal of Nuclear Science and Technology, 1997Co-Authors: Taisuke Yonomoto, Masaya Kondo, Yutaka KukitaAbstract:Investigation of thermal-Hydraulic Phenomena under natural circulation conditions at low pressures is important for development of a next-generation PWR relying on a secondary depressurization system (SDS) and gravity-driven safety injection system (GDIS) for long-term core cooling. Such Phenomena have not been sufficiently investigated so far since they do not have significant importance in the safety analysis for the conventional PWRs. A loss-of-coolant accident test was conducted at the ROSA-V/LSTF, a large scale PWR simulator, using the SDS, GDIS and a flashing-driven safety injection system (FDIS) which is a newly proposed safety system in this study. The FDIS, unlike the conventional accumulator injection system, does not have a potential to bring noncondensable gas into the primary system and thus is advantageous for those reactor designs which rely on the SDS. From analyses of the test results, the effectiveness of the combined use of the SDS and GDIS on the long-term core cooling was confirmed, important thermal-Hydraulic Phenomena and characteristics of the FDIS were clarified, and the problems of the RELAP5/MOD3 code to predict low pressure behavior were identified.
