Zobrazeno 1 - 10
of 12
pro vyhledávání: '"Seihiro ITOYA"'
Publikováno v:
Journal of Nuclear Science and Technology. 28:258-267
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::80e0338edc1e3486ff56c1e13b3b45b3
https://doi.org/10.1080/18811248.1991.9731352
https://doi.org/10.1080/18811248.1991.9731352
Publikováno v:
Nuclear Technology. 77:32-45
Simulation tests of a boiling water reactor (BWR) loss-of-coolant accident (LOCA) caused by a double-ended guillotine break of a recirculation pump suction line were carried out with the rig of safety assessment III (ROSA-III) test facility at the Ja
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3d1f2853e0fe568a1a1924ece4c4d4ca
https://doi.org/10.13182/nt87-a33949
https://doi.org/10.13182/nt87-a33949
SAFER03 and TRAC-BD1 analyses of TBL experiments on a boiling water reactor loss-of-coolant accident
Autor:
Nobuaki Abe, Seihiro Itoya
Publikováno v:
Nuclear Engineering and Design. 97:297-311
Simulation tests of a BWR LOCA were conducted with a Two Bundle Loop (TBL). Japanese BWR utilities, Toshiba Corp. and Hitachi Ltd. have jointly performed the SAFER03 and TRAC-BD1 code analyses with the TBL test data. The objective of this study is to
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::543231159570a46f9b0806899575e101
https://doi.org/10.1016/0029-5493(86)90166-4
https://doi.org/10.1016/0029-5493(86)90166-4
Publikováno v:
Nuclear Technology. 80:349-359
The advanced boiling water reactor (ABWR) is designed to represent the next generation of boiling water reactors (BWRs), to be introduced into commercial operation in the 1990s. The response of the ABWR to loss-of-coolant accidents (LOCAs) was simula
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::05987bb998712664267656977b316af0
https://doi.org/10.13182/nt88-a34059
https://doi.org/10.13182/nt88-a34059
Publikováno v:
Journal of Nuclear Science and Technology. 25:295-311
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ba18d3a3dfb0a00f40e2d18600ab28ed
https://doi.org/10.1080/18811248.1988.9733590
https://doi.org/10.1080/18811248.1988.9733590
Autor:
Samir M. Sami, C. H. Le, Jack L. Collins, Morris F. Osborne, R. A. Lorenz, Seihiro Itoya, Masami Kato, Nobuaki Abe, Hideo Nagasaka, Haim Tobias, Efraim Taragan, Yoram Oren, Abraham Soffer, Timothy S. Roth, A. Biancheria, Hideo Hirayama, Dick Duffey, Peter F. Wiggins, Philippe J. Vernier, Philippe Solignac, Y. L. Yuan, R. P. Gardner, K. Verghese, Cheng-Hsin Mao, Pao-Shan Weng, Gerard L. Hofman
Publikováno v:
Nuclear Technology. 77:1-5
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9071dc773ef854d24b3d7150b93d9511
https://doi.org/10.13182/nt87-a33946
https://doi.org/10.13182/nt87-a33946
Publikováno v:
Journal of Nuclear Science and Technology. 21:538-549
Two simulation tests for a boiling water reactor large loss-of-coolant accident (LOCA), conducted in the two bundle loop, were analyzed using the current licensing code system. These tests were recirculation-pump suction-line double-ended break tests
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d004e713f4c0496dc0ad9a018a0085fd
https://doi.org/10.1080/18811248.1984.9731079
https://doi.org/10.1080/18811248.1984.9731079
Publikováno v:
Journal of Nuclear Science and Technology. 24:639-652
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::08631097cf07c07ddeec10831f5ee212
https://doi.org/10.1080/18811248.1987.9735860
https://doi.org/10.1080/18811248.1987.9735860
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Akademický článek
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