KIKUCHI Akira | Division of Nuclear Safety Research, Japan Atomic Energy Research Institute
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Division of Nuclear Safety Research, Japan Atomic Energy Research Institute | 論文
- Effect of burst temperature on coolant channel restriction in multirods burst tests.
- Zircaloy-clad fuel rod burst behavior under simulated loss-of-coolant condition in pressurized water reactors.
- Oxygen embrittlement for zircaloy cladding.
- Effect of fuel pellet eccentricity with cladding on fuel rod thermal behavior under reactivity initiated accident condition.
- Zircaloy-4 cladding embrittlement due to inner surface oxidation under simulated loss-of-coolant condition.