Fission Products Release form Irradiated FBR MOX Fuel during Transient Conditions
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概要
- 論文の詳細を見る
Out-of-pile experiments on the release of fission products (FPs) under transient heating conditions were carried out for mixed oxide fuels. The fuels used in the experiments, the plutonium content of which was 30 wt%, were irradiated up to 65 GWd/t in the experimental fast reactor JOYO. The experiments consisted of two runs, FP-1 and FP-2. In FP-1, the fuel sample was first heated to 2,000°C and then up to 3,000°C. The holding time was 30 min at each temperature. In FP-2, the terminal temperatures were 1,500°C and 2,500°C, and the holding time was 30 min in the same manner.The release of Cs, a volatile FP, was detected as soon as the fuel sample was heated up. The release rate, after peaking in several minutes, decreased gradually via a diffusion process in the fuel matrix. The “gross” diffusion coefficient agreed well with the data reported in other experiments using LWR fuels. The release fractions were identical in both experiments, namely Cs ∼100%, Sb ∼100%, Ru ∼10%, Ce ∼0% and Eu ∼0%.
- 社団法人 日本原子力学会の論文
- 2003-02-25
著者
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Namekawa Takashi
O-arai Engineering Center Japan Nuclear Fuel Cycle Development Institute
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SATO Isamu
O-arai Engineering Center, Japan Nuclear Fuel Cycle Development Institute
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NAKAGIRI Toshio
O-arai Engineering Center, Japan Nuclear Fuel Cycle Development Institute
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HIROSAWA Takashi
O-arai Engineering Center, Japan Nuclear Fuel Cycle Development Institute
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MIYAHARA Sinya
O-arai Engineering Center, Japan Nuclear Fuel Cycle Development Institute
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Sato Isamu
O-arai Engineering Center Japan Nuclear Fuel Cycle Development Institute
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Miyahara Sinya
O-arai Engineering Center Japan Nuclear Fuel Cycle Development Institute
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Hirosawa Takashi
O-arai Engineering Center Japan Nuclear Fuel Cycle Development Institute
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Hirosawa Takashi
O-arai Engineering Center Japan Nuclear Cycle Development Institute
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Nakagiri Toshio
O-arai Engineering Center Japan Nuclear Fuel Cycle Development Institute
関連論文
- Fission Products Release form Irradiated FBR MOX Fuel during Transient Conditions
- Melting Temperature of Mixed Oxide Fuels for Fast Reactors
- Melting Temperature of Irradiated Fast Reactor Mixed Oxide Fuels
- Melting Temperature of Simulated High-Burnup Mixed Oxide Fuels for Fast Reactors
- Fission Products Release form Irradiated FBR MOX Fuel during Transient Conditions