Zobrazeno 1 - 7
of 7
pro vyhledávání: '"Lainsu Kao"'
Autor:
Lainsu Kao, Show-Chyuan Chiang
Publikováno v:
Nuclear Technology. 149:265-280
The work described in this paper is benchmark calculations of pressurization transient turbine trip tests performed at the Peach Bottom boiling water reactor (BWR). It is part of an overall effort in providing qualification basis for the INER/TPC BWR
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9a74a9ee3c4f9fc246c842a19e6f0c6d
https://doi.org/10.13182/nt05-a3595
https://doi.org/10.13182/nt05-a3595
Publikováno v:
Nuclear Technology. 129:51-68
The very first work on RETRAN model development and its application to plant design study for the Lungmen nuclear power station (LMNPS) is presented. Lungmen is the fourth nuclear power plant of the Taiwan Power Company (TPC). LMNPS has two advanced
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f32ef545b169d9567541b66146fbc33c
https://doi.org/10.13182/nt00-a3045
https://doi.org/10.13182/nt00-a3045
Autor:
Lainsu Kao, Ping-Hue Huang
Publikováno v:
Nuclear Technology. 127:382-388
The reactor coolant pump locked rotor analysis methodology developed by Taiwan Power Company for application to pressurized water reactors (PWRs) is presented. The proposed locked rotor analysis methodology utilizes two computer codes developed or sp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f883bc14f478ff79b494e563ad5bd050
https://doi.org/10.13182/nt99-a3008
https://doi.org/10.13182/nt99-a3008
Publikováno v:
Nuclear Technology. 121:324-336
The RETRAN analyses of three areas of thermal-hydraulic concerns are presented. The first evaluated whether a 360-deg through-wall crack could be detected based on system response with leakage through the crack. The second analysis was to identify th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::de0f94aa96f7e48e60e550a7db04fcea
https://doi.org/10.13182/nt98-a2844
https://doi.org/10.13182/nt98-a2844
Publikováno v:
Nuclear Technology. 121:302-312
Two analyses for Chinshan nuclear power station (CSNPS) show the RETRAN applications in reactor operations. One was used to find the root cause of a reactor trip due to high neutron flux (APRM Hi-Hi). Two of the four turbine control valves failed and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::92d97b9268ae301ce3131086898f69a6
https://doi.org/10.13182/nt98-a2842
https://doi.org/10.13182/nt98-a2842
Autor:
Lainsu Kao, Mujid S. Kazimi
Publikováno v:
Nuclear Technology. 78:170-184
Analyses of the concrete attack and ex-vessel aerosol release using various assumptions for the molten corium/concrete interaction have been performed. The study involved variations in several parameters, such as initial debris temperature, amount of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6597275292f33da959919b0fc7d2175e
https://doi.org/10.13182/nt87-a33995
https://doi.org/10.13182/nt87-a33995
Autor:
Nicolay Ivanov Kolev, Kohyu Fukunishi, Satoshi Suzuki, Masafumi Itagaki, Jun-ichi Abe, Katsuaki Kuribayashi, John F. Geldard, Adolph L. Beyerlein, Houn-lin Chiu, Morris F. Osborne, Jack L. Collins, Richard A. Lorenz, Lainsu Kao, Mujid S. Kazimi, Tatsuo Izumida, Fumio Kawamura, Koichi Chino, Makoto Kikuchi, Nasir Majid Mirza, Ansar Parvez
Publikováno v:
Nuclear Technology. 78:91-94
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::992309c1ac6fb2a4471085ef6bf7bd5c
https://doi.org/10.13182/nt87-a33989
https://doi.org/10.13182/nt87-a33989