Zobrazeno 1 - 10
of 67
pro vyhledávání: '"Hao-Tzu Lin"'
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2012 (2012)
In this paper, the TRACE model for IIST facility is developed and verified with the Small Break loss of coolant accident (SBLOCA) experiment of IIST (Institute of Nuclear Energy Research Integral System Test) facility. By using the Wallis and Kutatel
Externí odkaz:
https://doaj.org/article/70533f8093fd4a279be7f750fe97cb1b
The evaluation of TRACE/PARCS model for BWR-4 nuclear power plant by startup test transient analyses
Publikováno v:
Kerntechnik. 86:353-364
Generally, the thermal hydraulic (TH) codes need the results of Neutron Kinetics (NK) codes providing the reactivity properties to calculate neutron flux. Then the TH codes perform the safety analyses obtaining the responses of pressure, temperature,
Publikováno v:
Kerntechnik. 86:128-142
This study established an RCS-Containment coupled model that integrates the reactor coolant system (RCS) and the containment system by using the TRACE code. The coupled model was used in both short-term and long-term loss of coolant accident (LOCA) a
Publikováno v:
Kerntechnik. 84:508-519
IIST (Institute of Nuclear Energy Research Integral System Test) facility is a RHRP (Reduced-Height and Reduced-Pressure) facility for the three-loop PWR (Pressurized Water Reactor) NPP (Nuclear Power Plant) Maanshan. This test facility was establish
Publikováno v:
Kerntechnik. 84:161-168
Kuosheng Nuclear Power Plant (NPP) is a BWR/6 plant in Taiwan. First, this study focuses on the establishment of the TRACE/SNAP model for Kuosheng. To check the system response of the Kuosheng TRACE/SNAP model, the Final Safety Analysis Report (FSAR)
Autor:
Min-Song Lin, Wei-Keng Lin, Jong-Rong Wang, Feng-Jiun Kuo, Chunkuan Shih, Min-Lun Chai, Jin-Der Lee, Hao Tzu Lin, Wan-June Chiu, Shao-Wen Chen
Publikováno v:
Microelectronics Reliability. 72:103-114
Heat pipes and two-phase heat transfer devices are widely used in electronics cooling, and the thermal resistance is a key issue to ensure the system performance and reliability. In this study, the traditional one dimensional (1D) and quasi-two dimen
Autor:
Hao-Tzu Lin, Wan-Yun Li, Jong-Rong Wang, Yung-Shin Tseng, Hsiung-Chih Chen, Chunkuan Shih, Shao-Wen Chen
Publikováno v:
Kerntechnik. 82:31-42
Chinshan nuclear power plant (NPP), a BWR/4 plant, is the first NPP in Taiwan. After Fukushima NPP disaster occurred, there is more concern for the safety of NPPs in Taiwan. Therefore, in order to estimate the safety of Chinshan NPP spent fuel pool (
Autor:
Kai-Chun Huang, Hao-Tzu Lin, Show-Chyuan Chiang, Jong-Rong Wang, Chia-Chuan Liu, Chunkuan Shih
Publikováno v:
Annals of Nuclear Energy. 89:1-18
Maanshan nuclear power plant (NPP) is a two-unit Westinghouse three-loop PWR NPP. This research focuses on the analysis and simulation of Maanshan NPP station blackout (SBO) accident that happened on 18th March, 2001, and thermal–hydraulic phenomen
Publikováno v:
Kerntechnik. 80:522-528
Lungmen nuclear power plant project started long time ago, it is not yet commercially operated but Taiwan Power Company has already prepared for its startup tests. 3RIP trip startup test is one of them. Three of the 10 RIPs will be manually tripped i
Publikováno v:
Kerntechnik. 80:431-439
Station blackout anticipated transient without scram (SBO ATWS) is considered as loss of off-site and on-site power but no credit for automatic reactor trip. SBO ATWS causes reactor coolant pump (RCP) trip, loss of all main feedwater pumps and turbin