Zobrazeno 1 - 10
of 14
pro vyhledávání: '"Chan Y. Paik"'
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 3966-3978 (2021)
ISFRA (Integrated SFR Analysis Program for PSA) computer program has been developed for simulating the response of the PGSFR pool design with metal fuel during a severe accident. This paper describes validation of the ISFRA aerosol model against the
Externí odkaz:
https://doaj.org/article/90e1fa815f07470b9829f9ee8bbc3073
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 12, Pp 3966-3978 (2021)
ISFRA (Integrated SFR Analysis Program for PSA) computer program has been developed for simulating the response of the PGSFR pool design with metal fuel during a severe accident. This paper describes validation of the ISFRA aerosol model against the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5b5c761967d07b9253e04e569452a793
https://doi.org/10.1016/j.net.2021.06.036
https://doi.org/10.1016/j.net.2021.06.036
Autor:
Shinya Mizokami, T. Okamoto, S. Kraft, F. Bolger, H. Tanoue, D. Luxat, R. Gauntt, W. Kikuchi, Richard M. Wachowiak, M. Corradini, A. Nakayoshi, P. Ellison, K. Robb, J. Gabor, W. Luangdilok, M. Plys, M. T. Farmer, L. Albright, M. Yasui, P. McMinn, M. Cibula, P. Whiteman, R. Linthicum, Chan Y. Paik, M. Kurata, S. Basu, K. Kirkland, S. Ito, N. Andrews, H. Hoshi, J. Rempe, K. Klass, M. Taira, T. Kobayashi, R. Kojo, R. Bunt, J. Nakano, K. Voelsing, K. Iwanaga, S. Koyama, P. Amway, M. Nudi, B. Williamson, R. Martin, T. Washiya
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::db79eb2e54ee663c518614fa2155f0af
https://doi.org/10.2172/1773089
https://doi.org/10.2172/1773089
Publikováno v:
Annals of Nuclear Energy. 116:290-295
A simple turbulent diffusion model is described for predicting late term mixing due to Rayleigh-Taylor instability at an interface that initially separates two semi-infinite regions of fluid of different densities. The one-dimensional, transient spec
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c501256ad07fb2a71f58bb7f555a678a
https://doi.org/10.1016/j.anucene.2018.02.042
https://doi.org/10.1016/j.anucene.2018.02.042
Autor:
Christopher Henry, R. Linthicum, John D. Gabor, R. Gauntt, Joy L. Rempe, Cristian Rabiti, R. Lutz, Wison Luangdilok, Paul B. Ellison, Chan Y. Paik, R. Bunt, M. Plys, R. Wachowiak, Mitchell T. Farmer, Michael L. Corradini, Kevin R Robb, M. Francis
Publikováno v:
Nuclear Science and Engineering. 184:293-304
The reactor accidents at Fukushima Daiichi have rekindled interest in light water reactor (LWR) severe accident phenomenology. Postevent analyses have identified several areas that may warrant addi...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::13c57d00752fa0fd1e932f4eeb34a228
https://doi.org/10.13182/nse16-13
https://doi.org/10.13182/nse16-13
Publikováno v:
Annals of Nuclear Energy. 147:107666
Prediction of the rate of fission product vaporization from a liquid metal pool to an overlying cover gas is important to both operational and safety (source term) considerations of fast reactors. The fission product vaporization rate can be strongly
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::766b18d82532df6e5edcd7692cdd4f28
https://doi.org/10.1016/j.anucene.2020.107666
https://doi.org/10.1016/j.anucene.2020.107666
Autor:
Willis Bixby, S. Kraft, C. Henry, M. Plys, R. Linthicum, Bill Williamson, Matthew W. Francis, Nathan Andrews, P. Ellison, R. Gauntt, D. Luxat, P. Humrickhouse, Richard M. Wachowiak, R. Bunt, J. Gabor, C. Negin, R. Sanders, R. Lutz, M. T. Farmer, J. Rempe, P. Amway, T. Farthing, Chan Y. Paik, Michael L. Corradini, Kevin R Robb, J. Maddox, W. Luangdilok
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::41d938663f4f2ed0b8f50eaecfc2bceb
https://doi.org/10.2172/1331672
https://doi.org/10.2172/1331672
Publikováno v:
Volume 2A: Thermal Hydraulics.
The Modular Accident Analysis Program (MAAP) is a computer code that is used for integrated severe accident analysis. The latest MAAP5 version was validated against the PHEBUS-PF FPT0 and FPT1 tests performed at CEA/IPSN, PBF-SFD Test 1–4 performed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e55d3dd4bc33f061d272568e4faf8040
https://doi.org/10.1115/icone22-30405
https://doi.org/10.1115/icone22-30405
Publikováno v:
Volume 2B: Thermal Hydraulics.
During a severe accident with a vessel failure, corium relocates from the vessel into the reactor cavity (PWR) or pedestal (BWR) and accumulates on top of the cavity floor to form a corium pool. This corium pool is hot enough to cause a Molten Corium
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::28d0a048e495defcf8c39c8c528c3eff
https://doi.org/10.1115/icone22-31220
https://doi.org/10.1115/icone22-31220
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