JENDL-4.0 Benchmarking for Fission Reactor Applications

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概要

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• 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.

著者

• Chiba Go

  Japan Atomic Energy Agency

• Okumura Keisuke

  Japan Atomic Energy Agency

• Okajima Shigeaki

  Japan Atomic Energy Research Institute

• ISHIKAWA Makoto

  Japan Nuclear Cycle Development Institute

• Sugino Kazuteru

  Japan Atomic Energy Agency

• NAGAYA Yasunobu

  Japan Atomic Energy Agency

• YOKOYAMA Kenji

  Japan Atomic Energy Agency

• KUGO Teruhiko

  Japan Atomic Energy Agency

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