Zobrazeno 1 - 10
of 12
pro vyhledávání: '"Katsuhiro Ohkawa"'
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 5
The low-pressure depressurization system (LPDS) of advanced passive pressurized water reactors (PWRs) is designed to provide depressurization of the reactor coolant system during a small break loss-of-coolant accident (LOCA). The liquid entrainment t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e44d86f1f1362dee0015c366f265a8c0
https://doi.org/10.1115/1.4042796
https://doi.org/10.1115/1.4042796
Publikováno v:
Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation.
During the reflood phase of a postulated large break loss-of-coolant accident (LBLOCA), the liquid head in the reactor vessel downcomer provides the driving force to reflood the core. Since the reflood rate is a function of the downcomer inventory, t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::30ee948cc9e3129bbbdccbb8670b89f2
https://doi.org/10.1115/icone26-82610
https://doi.org/10.1115/icone26-82610
Publikováno v:
Nuclear Engineering and Design. 295:239-250
For the two-phase flow in a horizontal pipe, individual phases may separate because of gravity. This horizontal stratification significantly impacts interfacial drag, interfacial heat transfer and wall drag of the two-phase flow. Due to the low inter
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7f9ac3e706da516730ba6d1cfee3e843
https://doi.org/10.1016/j.nucengdes.2015.09.023
https://doi.org/10.1016/j.nucengdes.2015.09.023
Publikováno v:
Nuclear Engineering and Design. 285:171-187
Direct contact condensation in the cold leg of pressurized water reactor is an important phenomenon during a postulated loss-of-coolant accident. The amount of condensation in the cold legs impacts the thermal hydraulic behavior of the reactor coolan
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::874f7c9beea641727dfefdbdf96ff792
https://doi.org/10.1016/j.nucengdes.2015.01.011
https://doi.org/10.1016/j.nucengdes.2015.01.011
Publikováno v:
Nuclear Engineering and Design. 225:191-217
The development of a fully-implicit scheme to model the two-phase three-field flow and heat transfer problem is presented here. The model was originally developed to simulate the complex phenomena occurring in proximity of the quench front of a nucle
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bc2fec8ae64807138dea9a5b881e628f
https://doi.org/10.1016/s0029-5493(03)00159-6
https://doi.org/10.1016/s0029-5493(03)00159-6
Publikováno v:
Nuclear Technology. 136:50-62
Since the 1988 Appendix K Rulemaking change, there has been significant interest in the development of codes and methodologies for 'best-estimate' analysis of loss-of-coolant accidents (LOCAs). Most development has been directed toward large-break (L
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::842558f8cf02c022ccf8a1e8cb1fae07
https://doi.org/10.13182/nt01-a3228
https://doi.org/10.13182/nt01-a3228
Publikováno v:
Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance.
Westinghouse realistic Large Break LOCA methodology (Frepoli, 2008) is based on the use of the WCOBRA/TRAC code (Young, et. al., 1998). The original COBRA/TRAC code (Thurgood, et. al., 1983) was developed at Pacific Northwest Laboratory by combining
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::42744d1362305504ab2111c10cc87dbc
https://doi.org/10.1115/icone17-76044
https://doi.org/10.1115/icone17-76044
Autor:
Cesare Frepoli, Katsuhiro Ohkawa
Publikováno v:
12th International Conference on Nuclear Engineering, Volume 3.
Many experiments have been conducted in the past with full-scale rod bundles to develop void fraction correlations or interfacial drag model which can be used to predict the mixture level in a reactor core following a postulated Loss of Coolant Accid
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0852e8f7ebcb46e50f04183faeb9710a
https://doi.org/10.1115/icone12-49437
https://doi.org/10.1115/icone12-49437
Publikováno v:
12th International Conference on Nuclear Engineering, Volume 3.
In 1988, the U.S. Nuclear Regulatory Commission (NRC) issued a revision to 10CFR50.46 which allows realistic calculations for loss-of-coolant accident/emergency core cooling system (ECCS) analysis. The revision also requires that uncertainties in the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e2b70de6ad194e77e5655b218b1eabe5
https://doi.org/10.1115/icone12-49499
https://doi.org/10.1115/icone12-49499
Autor:
Cesare Frepoli, Katsuhiro Ohkawa
Publikováno v:
The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2003:273
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ebb4e1e53eb4ea778bf664729f3467dc
https://doi.org/10.1299/jsmeicone.2003.273
https://doi.org/10.1299/jsmeicone.2003.273