2024 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 301-1 Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[1L04-07] JENDL-5 Utilization

Tue. Mar 26, 2024 10:50 AM - 11:55 AM Room L (21Bildg.4F 21-423)

Chair:Tatsuya Fujita(JAEA)

11:05 AM - 11:20 AM

[1L05] Analysis of post-irradiation examination by SWAT4 with the JENDL-5 cross-section data

*Tomoaki Watanabe1, Takeo Kikuchi1, Yuta Kasuya2, Takuro Nomura3, Kenya Suyama1 (1. JAEA, 2. Univ. of Fukui, 3. TCU)

Keywords:JENDL-5, SWAT4, Post irradiation examination analysis, Burnup calculation

Several post-irradiation examination data were analyzed by SWAT4 with the cross section data of JENDL-5. The differences in the analysis results due to the change of cross-section data from JENDL-4.0 to JENDL-5 and the effects of the reactor type and fuel type of the PIE data on these differences were confirmed.

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