Effects of radial core power profile on core thermo-hydraulic behavior during reflood phase in SCTF CORE-I forced feed tests
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Tokai-mura, Naka-gun, Ibaraki-ken:
Japan Atomic Energy Research Institute,
1991.
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| Physical Description: | vi, 89 p.: ill.; 30 cm.. |
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| Bibliography: | Includes bibliographical references |