JENDL-4.0 Benchmarking for Fission Reactor Applications
スポンサーリンク
概要
- 論文の詳細を見る
Benchmark testing for the newly developed Japanese evaluated nuclear data library JENDL-4.0 is carried out by using a huge amount of integral data. Benchmark calculations are performed with a continuous-energy Monte Carlo code and with the deterministic procedure, which has been developed for fast reactor analyses in Japan. Through the present benchmark testing using a wide range of benchmark data, significant improvement in the performance of JENDL-4.0 for fission reactor applications is clearly demonstrated in comparison with the former library JENDL-3.3. Much more accurate and reliable prediction for neutronic parameters for both thermal and fast reactors becomes possible by using the library JENDL-4.0.
- 2011-02-01
著者
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Chiba Go
Japan Atomic Energy Agency
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Okumura Keisuke
Japan Atomic Energy Agency
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Okajima Shigeaki
Japan Atomic Energy Research Institute
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ISHIKAWA Makoto
Japan Nuclear Cycle Development Institute
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Sugino Kazuteru
Japan Atomic Energy Agency
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NAGAYA Yasunobu
Japan Atomic Energy Agency
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YOKOYAMA Kenji
Japan Atomic Energy Agency
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KUGO Teruhiko
Japan Atomic Energy Agency
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奥村 啓介
日本原子力研究開発機構 原子力基礎工学研究部門
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Okumura Keisuke
Department Of Nuclear Energy System Japan Atomic Energy Research Institute
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Okumura Keisuke
Japan Atomic Energy Research Institute
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Okajima Shigeaki
Japan Atomic Energy Agency
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Ishikawa Makoto
Japan Atomic Energy Agency
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Okumura Keisuke
Nuclear Science And Engineering Directorate Japan Atomic Energy Agency
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