Zobrazeno 1 - 9 of 9 pro vyhledávání: '"Noboru Nakao"'
1
A Method for Improvement of Safety Features of Large Fast Breeder Reactors
Autor: Tomoko Murakami, Noboru Nakao, Yoshio Watari, Katsuyuki Kawashima, Masanori Miura, Masayoshi Ishida
Publikováno v: Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan. 37:327-337
Numerical simulation of an unprotected loss-of-flow( ULOF) accident has been performed for a large liquid-metal-cooled fast breeder reactor (LMFBR) equipped with gas expansion modules (GEMs) in the radial periphery of the reactor core. The effectiven
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::8e938da5f62c576d4969924db2b7e9a9
https://doi.org/10.3327/jaesj.37.327
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2
Current Status of Development of Demonstration Fast Breeder Reactor and Prospect of FBR Commercialization
Autor: Masahiro Ueta, Masamichi Matsuda, Tatsutoshi Inagaki, Tsutomu Yanagisawa, Kenzou Hida, Takeshi Kobayashi, Hiroto Kawakami, Noboru Nakao, Masanori Miura
Publikováno v: Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan. 37:112-123
The Demonstration Fast Breeder Reactor (DFBR) is the next step of FBR development following the prototype fast breeder reactor "MONJU". The DFBR is now under development by The Japan Atomic Power Co. (JAPC) under the sponsorship of 9 Japanese electri
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::433460b1f42fe00170a4b53fcea8f3a7
https://doi.org/10.3327/jaesj.37.112
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4
A Survey of Dogs from Gifu and Shiga Area for Brucella canis
Autor: Noboru Nakao, Tadao Serikawa, Takehiko Muraguchi
Publikováno v: The Japanese Journal of Veterinary Science. 39:635-642
A total of 1, 186 dogs from Gifu and Shiga area were surveyed for Brucella canis (B. canis) during a year from April, 1976 to March, 1977. The dogs with serum agglutinin titer of 1:320 or higher against B. canis were sacrificed and their various orga
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4d8bac6b27d0d2a38f4397e6a7bf67a0
https://doi.org/10.1292/jvms1939.39.635
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5
Diana — A fast and high capacity computer code for interchannel coolant mixing in rod arrays
Autor: Seizo Hirao, Noboru Nakao
Publikováno v: Nuclear Engineering and Design. 30:214-222
A mathematical model and digital computer program are presented for the subchannel thermal and hydraulic analysis of sodium-cooled fast reactor fuel assemblies. The newly developed FORTRAN-IV computer code ‘DIANA’ is much more useful than many ot
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::c2e037906b88a0892a539bba7f44f62e
https://doi.org/10.1016/0029-5493(74)90166-6
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6
Channel deformation analysis for fast reactor fuel assemblies undergoing swelling and thermal bowing
Autor: Seizo Hirao, Akikazu Morino, Kenichi Ohmae, Noboru Nakao
Publikováno v: Nuclear Engineering and Design. 23:309-320
Differential thermal expansion and swelling of fuel pins, hexagonal flow ducts and fuel spin spacers, fuel pin bowing between the spacers due to subchannel temperature differentials, and fuel pin bundle bowing due to the cambered hexagonal wrapper tu
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::45f9fe6b8cdf053d7340957744e96393
https://doi.org/10.1016/0029-5493(72)90152-5
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9
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