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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

Main Author: Iwamura, Takamichi
Corporate Author: Japan Atomic Energy Research Institute
Other Authors: Osakabe, Masahiro, Sobajima, Makoto, Sudo, Yukio
Published: Tokai-mura, Naka-gun, Ibaraki-ken: Japan Atomic Energy Research Institute, 1991.
Subjects:
PWR type reactors
Reflood
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Physical Description:vi, 89 p.: ill.; 30 cm..
Bibliography:Includes bibliographical references

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