JENDL-4.0 benchmarking for fission reactor applications

Chiba, Go; Okumura, Keisuke ; Sugino, Kazuteru; Nagaya, Yasunobu  ; Yokoyama, Kenji   ; Kugo, Teruhiko ; Ishikawa, Makoto; Okajima, Shigeaki  

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 may become possible by using the library JENDL-4.0.