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PWR type reactors
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Effects of radial core power profile on core thermo-hydraulic behavior during reflood phase in SCTF CORE-I forced feed tests Takamichi Iwamura ... [et al.].
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Iwamura, Takamichi
Published 1991
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Japan Atomic Energy Research Institute
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Osakabe, Masahiro
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Sobajima, Makoto
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Sudo, Yukio
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