An optimization study of structure materials, coolant and tritium breeding materials for nuclear fusion-fission hybrid reactor
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- Ishibashi Kyosuke
- Tokyo City University
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- Fujimoto Shintaro
- Tokyo City University
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- Matsumoto Tetsuo
- Tokyo City University
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抄録
The blanket materials were evaluated and optimized for use in a nuclear fusion-fission hybrid reactor by calculating the tritium breeding ratio (TBR), the ratio of thermal power output to fusion power input (Q value) and the temperature distributions. The calculation of TBR and Q value was performed by Monte Carlo code (MCNP-4C) and the temperature distributions by one dimensional heat equation. First, the structure materials, coolant and tritium breeding materials were investigated in terms of the TBR and the Q value. Secondly, the layer structure was optimized by calculating the temperature distributions in the blanket where the materials were selected by considering the former results of the TBR and Q value. As a result, the highest TBR and Q value could be obtained, if vanadium alloy structure material, helium gas coolant and molten salt tritium breeding material would be used as the blanket material. In addition, by optimizing the blanket structure using these materials, it would be possible to get a high TBR of 2.0 maintaining the temperature limit of the blanket materials, and about twenty times the thermal power output could be produced compared to the fusion power input under the condition of effective multiplication factor of 0.80.
収録刊行物
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- Progress in Nuclear Science and Technology
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Progress in Nuclear Science and Technology 4 130-133, 2014
Atomic Energy Society of Japan
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詳細情報 詳細情報について
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- CRID
- 1390006750772093056
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- NII論文ID
- 40020092026
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- NII書誌ID
- AA12785802
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- NDL書誌ID
- 025518144
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- ISSN
- 21854823
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- NDL
- Crossref
- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可