スポンサーリンク
Division of Nuclear Safety Research, Japan Atomic Energy Research Institute | 論文
- 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.
- Measurement and evaluation on pulsing characteristics and experimental capability of NSRR.
- Effect of burst temperature on coolant channel restriction in multirods burst tests.
- Embrittlement of zircaloy-4 due to oxidation in environment of stagnant steam.
- Zircaloy-clad fuel rod burst behavior under simulated loss-of-coolant condition in pressurized water reactors.
- Oxygen embrittlement for zircaloy cladding.
- Acceleration of zircaloy-steam reaction rate by deformation under high temperature transient.
- Ductility loss of zircaloy cladding by inner-surface oxidation during high temperature transient.