Fission Gas Release from Externally Restrained Uramium Dioxide Fuel
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概要
- 論文の詳細を見る
In order to examine the fission gas release behavior under restraint conditions, an out-of-pile high pressure annealing technique was applied to UO2 fuels irradiated to 37 GWd/t in a BWR. The irradiated fuels were annealed at temperatures of 1,500–1,800°C and external pressures of 10–150 MPa. The fractional release of 85Kr was evaluated by β-activities in small amounts of gas that were intermittently collected from the high pressure furnace. The fission gas release was almost completely suppressed by strong external restraint pressures of 100–150 MPa in the temperature range of 1,500–1,800°C, and the critical pressure for the onset of burst release due to rapid bubble growth and tunnel formation was found to be in the range of 40–60 MPa at 1,500°C. This type of burst release was very similar to that observed during the power-down stage in the irradiation tests of high burnup fuels.
- 一般社団法人 日本原子力学会の論文
著者
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Une K
Global Nuclear Fuel‐japan Co. Ltd. Ibaraki
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Une Katsumi
Nippon Nuclear Fuel Development Co. Ltd.
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KASHIBE Shinji
Nippon Nuclear Fuel Development Co., Ltd.
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Kashibe Shinji
Nippon Nuclear Fuel Development Co. Ltd.
関連論文
- Effect of Gd_2O_3 Dispersion on the Thermal Conductivity of UO_2
- Heat Capacity Measurements of U_Gd_yO_2 (y=0-0.27) from 325 to 1,673K
- Fission Gas Release from Externally Restrained Uramium Dioxide Fuel
- Formation of Peller-Cladding Bonding Layer in High Burnup BWR Fuels
- Densification and Swelling in UO_2 Pellets under Hydrostatic Pressure Condition
- Fission Gas Release Behavior from High Burnup UO_2 Fuels under Rapid Heating Conditions
- Thermal Expansion of UO2-Gd2O3 Fuel Pellets