Zobrazeno 1 - 10
of 40
pro vyhledávání: '"Show-Chyuan Chiang"'
Autor:
Chunkuan Shih, Show-Chyuan Chiang, Jong-Rong Wang, Wen-Shu Huang, Wan-Yun Li, Tzu-Yao Yu, Shao-Wen Chen
Publikováno v:
Annals of Nuclear Energy. 112:655-665
In this study, the model of Lungmen ABWR NPP (nuclear power plant) using RELAP5 with the interface SNAP was established. This RELAP5/SNAP model performed the mitigation strategy simulation and study. The main systems of the mitigation strategy are RC
Autor:
Chunkuan Shih, Wen-Sheng Hsu, Jong-Rong Wang, Show-Chyuan Chiang, Yu Chiang, Hsiung-Chih Chen, Ting-Yi Wang, Shao-Wen Chen
Publikováno v:
Nuclear Engineering and Design. 325:12-24
After Fukushima Daiichi disaster, the safety analysis of severe accidents became one of the safety concerns in Taiwan. At the same time, Taiwan Power Company built up an event basis strategy called Ultimate Response Guideline (URG) to cope with the a
Autor:
Ting-Yi Wang, Chunkuan Shih, Jong-Rong Wang, Yu Ting Hsu, Show Chyuan Chiang, Tzu Yao Yu, Shao Wen Chen
Publikováno v:
Applied Mechanics and Materials. 865:701-706
After the Fukushima Daichii accidents, Taiwan Power Company developed a strategy to cope with such extended SBO (Station Blackout) cases at nuclear power plants, which called URG. The MAAP and PCTRAN were used to perform the study for Kuosheng BWR/6
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
Autor:
Show-Chyuan Chiang, Tzu-Yao Yu, Te-Chuan Wang, Hsiung-Chih Chen, Chunkuan Shih, Hao-Tzu Lin, Shao-Wen Chen, Wen-Sheng Hsu, Jong-Rong Wang, Yu Chiang
Publikováno v:
Proceedings of The 20th Pacific Basin Nuclear Conference ISBN: 9789811023101
Chinshan Nuclear Power Plant (NPP) was built in 1970 and is a BWR/4 NPP. The original rated power of Chinshan NPP for each unit is 1775 MW. Chinshan NPP finished the project of SPU (stretch power uprate) and the operating power is 1840 MW now. In ord
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eb48e7af17f1d105e57fd41d797377f2
https://doi.org/10.1007/978-981-10-2311-8_66
https://doi.org/10.1007/978-981-10-2311-8_66
Autor:
B.S. Pei, Chung-Yu Yang, Show-Chyuan Chiang, Thomas K.S. Liang, L. C. Dai, Chunkuan Shih, Lance L. C. Wang
Publikováno v:
Nuclear Engineering and Design. 249:41-48
Lungmen nuclear power plant is the first advanced boiling water reactor (ABWR) plant in Taiwan. According to the most up-to-date schedule, Lungmen Plant will begin its power tests in later 2011. The tests contain (1) loss of feedwater heater test, (2
Publikováno v:
Annals of Nuclear Energy. 40:122-129
Protecting the public from radiation exposure is important if a nuclear power plant (NPP) accident occurs. Deciding appropriate protective actions in a timely and effective manner can be fulfilled by using an effective accident evaluation tool. In ou
An Out-of-Box Approach to Integrate an Optimization Algorithm and MAAP5 for Parameter Identification
Publikováno v:
Nuclear Technology. 172:237-245
The modular accident analysis program (MAAP) is a fast-running severe accident analysis tool with which the timing of key events and source terms in a severe accident are assessed. The idea of combining MAAP and an optimization algorithm to identify
Publikováno v:
Nuclear Engineering and Design. 240:2842-2846
The minimum number of safety/relief valves (SRVs) required for emergency depressurization (MNSRED) is an important reactor pressure vessel (RPV) parameter described in the appendix C of BWR Owners’ Group, Emergency Procedure Guidelines and Severe A
Publikováno v:
Nuclear Technology. 169:50-60
The limiting blowdown event for the design of an advanced boiling water reactor (ABWR) containment shifts from a conventional recirculation line break to a feedwater line break (FWLB) by implementing reactor internal pumps. As a result, coupled blowd