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Publications by Masaru KATOH
Thermal Hydraulic Behavior in Upper Plenum During Refill-Reflood Phase of BWR LOCA, (II)
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Related publications
Quantitative Evaluation of ECCS Capability During Refill-Reflood Phase for BWR LOCA
Journal of Nuclear Science and Technology
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Upper Plenum Dump During Reflood in PWR Loss-Of-Coolant Accident
Journal of Nuclear Science and Technology
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Analytical Study of Thermal Response Similarity Between Simulated Fuel Rods and Nuclear Fuel Rods During Reflood Phase of PWR-LOCA
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Effects of Radial Core Power Profile on Core Thermo-Hydraulic Behavior During Reflood Phase in PWR-LOCAs.
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Neutron-Coupled Thermal Hydraulic Calculation of BWR Under Seismic Acceleration
Progress in Nuclear Science and Technology
Proving Test on Thermal-Hydraulic Performance of BWR Fuel Assemblies
Transactions of the Atomic Energy Society of Japan
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Reliability
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A Validation of ATR LOCA Thermal-Hydraulic Code With a Statistical Approach
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Evaluation of Thermal Margin During BWR Neutron Flux Oscillation.
Journal of Nuclear Science and Technology
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Thermal-Hydraulic Analysis of Semiscale Mod-1 Integral Blowdown-Reflood Tests (Baseline ECC Test Series)