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Journal Articles

Initial verification and validation of a new CASMO5 JENDL-5 nuclear data library for typical LWR applications

Watanabe, Tomoaki; Suyama, Kenya; Tada, Kenichi; Ferrer, R. M.*; Hykes, J.*; Wemple, C. A.*

Nuclear Science and Engineering, 10 Pages, 2024/00

 Times Cited Count:0 Percentile:0.08(Nuclear Science & Technology)

A new nuclear data library for the advanced lattice physics code CASMO5 has been prepared based on JENDL-5. In JENDL-5, many essential nuclides for conventional LWR analysis have also been modified based on state-of-the-art evaluations. The new JENDL-5-based CASMO5 library was prepared by replacing as much of the nuclear data of the current CASMO5 ENDF/B-VII.1-based library as possible with JENDL-5. This study verified and validated the new library. Verifications were performed based on the OECD/NEA burnup credit criticality safety benchmark phase III-C, and the calculated k$$_{inf}$$ and fuel compositions of the BWR fuel assembly were compared with reported benchmark results. Comparison with the MCNP6.2 result was also performed using the same benchmark model. In addition, the TCA critical experiment and Takahama-3 post-irradiation experiment were used for validation. The results indicate that the new library performs well and is comparable to the ENDF/B-VII.1-based library in predictions of reactivity and fuel compositions for LWR systems.

Oral presentation

Development and validation of CASMO5 library based on JENDL-5

Watanabe, Tomoaki; Suyama, Kenya; Tada, Kenichi; Ferrer, R.*; Hykes, J.*

no journal, , 

The CASMO5 neutron data library based on JENDL-5 is generated and validated by comparison with the conventional ENDF/B-VII.1 library analyzing TCA criticality experiments and Takahama-3 PIE data. In the present library, such data as cross section, decay data, fission yield, etc based on ENDF/B-VII.1 are replaced by those of JENDL-5 as much as possible. As a result of the TCA experiment analysis, k$$_{eff}$$ with the JENDL-5 library is slightly greater than those with the ENDF/B-VII.1 library for all cases analyzed. This tendency is also observed by same analysis using MVP3.0. For the PIE analysis, C/E values of nuclide inventory are almost comparable to those with the ENDF/B-VII.1 library and improved for a few nuclides such as Cs.

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