Zobrazeno 1 - 10
of 13
pro vyhledávání: '"Yin-Pang Ma"'
Publikováno v:
Nuclear Technology. 136:186-196
Multidimensional thermal-hydraulic characteristics in the secondary side of a steam generator (SG) are simulated by way of flow-boiling models. These models essentially belong to the so-called first-principle models that are derived from the conserva
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6f5c6e160550702304542eca7ac3a8b2
https://doi.org/10.13182/nt01-a3237
https://doi.org/10.13182/nt01-a3237
Autor:
K. Ting, Yin Pang Ma
Publikováno v:
Nuclear Engineering and Design. 191:231-243
Taiwan Pressurized Water Reactor (PWR), Maanshan nuclear power plant Units 1 and 2 implemented measurements of the wall thinning of the carbon steel piping under the request of regulation authority to prevent the events due to erosion/corrosion since
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8567688013a1bab09240a1dbd4423190
https://doi.org/10.1016/s0029-5493(99)00145-4
https://doi.org/10.1016/s0029-5493(99)00145-4
Publikováno v:
Nuclear Technology. 126:319-330
Flow-assisted corrosion (FAC), an aspect of erosion/corrosion (E/C), is a mechanism of piping degradation that causes a loss of material from the inside of the piping and then thinning of the wall....
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::942e94d673d2bcf98cd1fae6799502e2
https://doi.org/10.13182/nt99-a2977
https://doi.org/10.13182/nt99-a2977
Publikováno v:
Nuclear Technology. 123:90-102
Flow-accelerated corrosion (FAC) is a piping degradation mechanism resulting in the loss of material from the inside of the piping that subsequently thins the wall. The FAC that causes costly plant...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::85072d05a215caf6bac32a4853e06c1b
https://doi.org/10.13182/nt98-a2882
https://doi.org/10.13182/nt98-a2882
Publikováno v:
Nuclear Technology. 94:124-133
The void fraction is one of the most important quantities in experimental studies of two-phase flow. Two simple and economical techniques to determine this quantity are developed and discussed. The...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ae22ad12e1c19e4c586961780f42b1bb
https://doi.org/10.13182/nt91-a16228
https://doi.org/10.13182/nt91-a16228
Publikováno v:
Nuclear Technology. 92:134-140
A physically based theoretical model of gas-liquid and steam-water two-phase flow in a horizontal tee-junction is developed. The model includes five independent equations: the mixture continuity eq...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c6cdc306a3febc53848652a07e2cc377
https://doi.org/10.13182/nt90-a34493
https://doi.org/10.13182/nt90-a34493
Autor:
Volker Rüdinger, Craig I. Ricketts, Jürgen G. Wilhelm, R. P. Pratt, B. L. Stewart, D. Loughborough, H.-G. Dillmann, H. Pasler, J. G. Wilhelm, Jürgen Furrer, Walter Weinländer, William A. Neuman, James L. Jones, Sümer Şahin, Floyd J. Wheeler, D. Kent Parsons, Brian L. Rushton, David W. Nigg, Chaung Lin, Ali E. Dabiri, William K. Hagan, Donald A. Swenson, Kenneth A. Krohn, Yin-Pang Ma, Bau-Shei Pei, Wei-Keng Lin, Yih-Yun Hsu, Yassin A. Hassan, Parvez Salim
Publikováno v:
Nuclear Technology. 92:1-6
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::af6b38dfd13f5143e7e773c40045e776
https://doi.org/10.13182/nt90-a34481
https://doi.org/10.13182/nt90-a34481
Publikováno v:
Nuclear Technology. 90:49-62
Due to the potential threat of reactor coolant system (RCS) overpressurization, loss-of-normal-feed-water (LONF) transients without reactor trip have received special attention in the analysis of pressurized water reactor (PWR) anticipated transients
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::063dbd843551121f458bc73f960c8eae
https://doi.org/10.13182/nt90-a34385
https://doi.org/10.13182/nt90-a34385
Autor:
Carolyn D. Heising, William S. Grenzebach, Edward C. Beahm, Steven R. Daish, William E. Shockley, Joram Hopenfeld, Paul G. Voillequé, Abdo A. Husseiny, Zeinab A. Sabri, S Keith Adams, Rodrigo J. Rodriguez, Bau-Shei Pei, Ge-Ping Yu, Guei-Ching Lin, Yin-Pang Ma, Imtiaz K. Madni, Erik G. Cazzoli, Mohsen Khatib-Rahbar, Richard D. Peters, Urban P. Jenquin, Langdon K. Holton, Sadao Hattori, Tadasu Takuma, Koshichi Nemoto, Masafumi Terada, Tamotsu Sano, Alois Höld
Publikováno v:
Nuclear Technology. 90:1-4
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::355d23d0b11a2bced752a3ee766c9628
https://doi.org/10.13182/nt90-a34380
https://doi.org/10.13182/nt90-a34380
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