The Study of Loss-of-Coolant Accident Parameter Identification for a BWR-4 PlantTSAI, Chih-Ming; WANG, Shih-Jen.Revue générale nucléaire (Paris). 2011, Num 5, pp 53-62, issn 0335-5004, 10 p.Conference Paper

AN OUT-OF-BOX APPROACH TO INTEGRATE AN OPTIMIZATION ALGORITHM AND MAAP5 FOR PARAMETER IDENTIFICATIONTSAI, Chih-Ming; WANG, Shih-Jen; CHIANG, Show-Chyuan et al.Nuclear technology. 2010, Vol 172, Num 3, pp 237-245, issn 0029-5450, 9 p.Article

Development of accumulator computational aid for determining RCS injection volumeWANG, Shih-Jen; CHIEN, Chun-Sheng; CHIANG, Show-Chyuan et al.Nuclear engineering and design. 2006, Vol 236, Num 12, pp 1330-1333, issn 0029-5493, 4 p.Article

Comparison of severe accident results among SCDAP/RELAP5, MAAP, and MELCOR codesWANG, Te-Chuan; WANG, Shih-Jen; TENG, Jyh-Tong et al.Nuclear technology. 2005, Vol 150, Num 2, pp 145-152, issn 0029-5450, 8 p.Article

Analysis of PWR RCS injection strategy during severe accidentWANG, Shih-Jen; CHIANG, Kwang-Sheng; CHIANG, Show-Chyuan et al.Nuclear technology. 2004, Vol 146, Num 2, pp 199-205, issn 0029-5450, 7 p.Article

DEVELOPMENT OF PARAMETER-IDENTIFICATION CAPABILITY FOR MAAP4 CODECHIEN, Chun-Sheng; WANG, Shih-Jen; CHIANG, Show-Chyuan et al.Nuclear technology. 2008, Vol 161, Num 3, pp 203-209, issn 0029-5450, 7 p.Article

Effectiveness of the raw-water system as a severe-accident-management measure in station blackout accidentsWANG, Te-Chuan; WANG, Shih-Jen; TENG, Jyh-Tong et al.Nuclear technology. 2006, Vol 156, Num 3, pp 347-359, issn 0029-5450, 13 p.Article

Investigation of containment flooding strategy for mark-III nuclear power plant with MAAP4SU, Wei-Nian; WANG, Shih-Jen; CHIANG, Show-Chyuan et al.Nuclear technology. 2005, Vol 150, Num 3, pp 251-262, issn 0029-5450, 12 p.Article

Analysis of severe accident management strategy for a BWR-4 nuclear power plantWANG, Te-Chuan; WANG, Shih-Jen; TENG, Jyh-Tong et al.Nuclear technology. 2005, Vol 152, Num 3, pp 253-265, issn 0029-5450, 13 p.Article

Simulation of a PWR reactor vessel level indicating system during station blackout with melcor 1.8.5WANG, Te-Chuan; WANG, Shih-Jen; TENG, Jyh-Tong et al.Nuclear technology. 2006, Vol 156, Num 2, pp 133-139, issn 0029-5450, 7 p.Article

A study on the minimum steam cooling pressure of EOP for BWR power plantsCHEN, Jyh-Jun; WANG, Shih-Jen; HUANG, Ya-Chuan et al.Nuclear engineering and design. 2011, Vol 241, Num 8, pp 3283-3289, issn 0029-5493, 7 p.Article

SIMPLIFICATION OF THE SEVERE ACCIDENT MANAGEMENT GUIDELINE FOR THE CONTAINMENT FLOODING IN A MARK-III CONTAINMENTCHUANG, Min-Jie; WANG, Shih-Jen; FANN, Sheng-Yuan et al.Nuclear technology. 2009, Vol 167, Num 2, pp 247-253, issn 0029-5450, 7 p.Article

A study on the boron injection initiation temperature curve of BWRWANG, Shih-Jen; CHIEN, Chun-Sheng; FANN, Sheng-Yuan et al.Nuclear engineering and design. 2007, Vol 237, Num 22, pp 2197-2200, issn 0029-5493, 4 p.Article

Analysis of Kuosheng station blackout accident using MELCOR 1.8.4WANG, Shih-Jen; CHIEN, Chien-Sheng; WANG, Te-Chuan et al.Nuclear technology. 2000, Vol 132, Num 2, pp 196-205, issn 0029-5450Article

A study of heat capacity temperature limit of BWRWANG, Shih-Jen; JYH JUN CHEN; CHIEN, Chun-Sheng et al.Nuclear engineering and design. 2012, Vol 243, pp 279-286, issn 0029-5493, 8 p.Article

Study on the minimum number of SRVs required for emergency depressurization in EOP of BWR power plantsCHIEN, Chun-Sheng; WANG, Shih-Jen; CHEN, Jyh-Jun et al.Nuclear engineering and design. 2010, Vol 240, Num 10, pp 2842-2846, issn 0029-5493, 5 p.Article

Analysis of pressurizer level control system using MAAP4 codeWANG, Yuan-Chien; WANG, Shih-Jen; CHIEN, Chun-Sheng et al.Nuclear engineering and design. 2010, Vol 240, Num 1, pp 160-165, issn 0029-5493, 6 p.Article

Development of drywell water level computational aid and application on containment flooding strategy of Mark-III nuclear power plantSU, Wei-Nian; WANG, Shih-Jen; HUANG, I-Ming et al.Nuclear technology. 2006, Vol 155, Num 3, pp 253-264, issn 0029-5450, 12 p.Article

Determination of BWR minimum steam cooling reactor water level and associated steam flow using MAAP4 codeCHEN, Jyh-Jun; WANG, Shih-Jen; CHIEN, Chun-Sheng et al.Nuclear engineering and design. 2010, Vol 240, Num 11, pp 3791-3796, issn 0029-5493, 6 p.Article