スポンサーリンク
Division of Reactor Safety, Japan Atomic Energy Research Institute | 論文
- Behavior of sodium oxide aerosol in closed chamber under thermal convection flow.
- Transient cooling process of fuel rod in reactivity initiated accident.
- 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.
- Boiling water reactor loss of coolant tests. Single failure tests with ROSA-III.
- Evaluation of effective energy deposition in test fuel during power burst experiment in NSRR.
- Zircaloy-clad fuel rod burst behavior under simulated loss-of-coolant condition in pressurized water reactors.
- Effects of coolant flow on light water reactor fuel behaviors during reactivity initiated accident.