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Search Results - Enuma, Yasuhiro
Search Results - Enuma, Yasuhiro
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Numerical simulation technologies for safety evaluation in plant lifecycle optimization method, ARKADIA for advanced reactors
by
Uchibori, Akihiro
,
Doda, Norihiro
,
Aoyagi, Mitsuhiro
,
Sonehara, Masateru
,
Sogabe, Joji
,
Okano, Yasushi
,
Takata, Takashi
,
Tanaka, Masaaki
,
Enuma, Yasuhiro
,
Wakai, Takashi
,
Asayama, Tai
,
Ohshima, Hiroyuki
Published in
Nuclear engineering and design
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Development of element functions and design optimization procedures for knowledge- and AI-aided advanced reactor lifecycle optimization method, ARKADIA
by
TANAKA, Masaaki
,
ENUMA, Yasuhiro
,
OKANO, Yasushi
,
UCHIBORI, Akihiro
,
YOKOYAMA, Kenji
,
SEKI, Akiyuki
,
WAKAI, Takashi
,
ASAYAMA, Tai
Published in
Mechanical Engineering Journal
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Development of element functions and design optimization procedures for knowledge- and AI-aided advanced reactor lifecycle optimization method, ARKADIA
by
TANAKA, Masaaki
,
ENUMA, Yasuhiro
,
OKANO, Yasushi
,
UCHIBORI, Akihiro
,
YOKOYAMA, Kenji
,
SEKI, Akiyuki
,
WAKAI, Takashi
,
ASAYAMA, Tai
Published in
Mechanical Engineering Journal
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Thermal transient test and strength evaluation of a tubesheet structure made of Mod.9Cr–1Mo steel. Part II: Creep-fatigue strength evaluation
by
Ando, Masanori
,
Hasebe, Shinnichi
,
Kobayashi, Sumio
,
Kasahara, Naoto
,
Toyoshi, Akira
,
Ohmae, Takahiro
,
Enuma, Yasuhiro
Published in
Nuclear engineering and design
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Thermal transient test and strength evaluation of a thick cylinder model made of Mod.9Cr-1Mo steel
by
Ando, Masanori
,
Hasebe, Shinnichi
,
Kobayashi, Sumio
,
Kasahara, Naoto
,
Toyoshi, Akira
,
Ohmae, Takahiro
,
Enuma, Yasuhiro
Published in
Nuclear engineering and design
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Effect of ratchet strain on fatigue and creep–fatigue strength of Mod.9Cr–1Mo steel
by
Ando, Masanori
,
Isobe, Nobuhiro
,
Kikuchi, Koichi
,
Enuma, Yasuhiro
Published in
Nuclear engineering and design
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Thermal transient test and strength evaluation of a tubesheet structure made of Mod.9Cr–1Mo steel. Part I: Test model design and experimental results
by
Ando, Masanori
,
Hasebe, Shinnichi
,
Kobayashi, Sumio
,
Kasahara, Naoto
,
Toyoshi, Akira
,
Ohmae, Takahiro
,
Enuma, Yasuhiro
Published in
Nuclear engineering and design
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Development of an unstable failure analysis procedure considering change of compliance at a crack part of SFR pipes
by
Wakai, Takashi
,
Machida, Hideo
,
Yoshida, Shinji
,
Yanagihara, Seiji
,
Suzuki, Ryosuke
,
Matsubara, Masaaki
,
Enuma, Yasuhiro
Published in
Engineering failure analysis
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System Analysis for Decay Heat Removal in Lead-Bismuth-Cooled Natural-Circulation Reactors
by
Sakai, Takaaki
,
Enuma, Yasuhiro
,
Iwasaki, Takashi
Published in
Nuclear technology
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