Session information

Oral presentation

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

[2H03-06] Analysis Code Development 1

Thu. Sep 17, 2020 10:40 AM - 11:55 AM Room H (Zoom room 8)

Chair:Hiroki Koike(MHI)

10:40 AM - 10:55 AM

[2H03] Development of FRENDY/MG

(1)Outline of multi-group cross section generation capability

*Akio Yamamoto¹, Tomohiro Endo¹, Go Chiba², Kenichi Tada³ (1. Nagoya University, 2. Hokkaido University, 3. JAEA)

10:55 AM - 11:10 AM

[2H04] Development of FRENDY/MG

(2)Multi-group cross section library generation for a code system CBZ

*Go Chiba¹, Akio Yamamoto² (1. Hokkaido University, 2. Nagoya University)

11:10 AM - 11:25 AM

[2H05] Investigation of the impact of difference between open nuclear data processing codes on neutron transport calculations

(3)Difference of nuclear data processing method

*Kenichi TADA¹, Tadashi IKEHARA¹, Michitaka ONO², Masayuki TOJO² (1. JAEA, 2. GNF-J)

11:25 AM - 11:40 AM

[2H06] Investigation of the impact of difference between open nuclear data processing codes on neutron transport calculations

(4)Investigation of the impact of difference between nuclear data processes on nuclear calculations

*Michitaka Ono¹, Masayuki Tojo¹, Kenichi Tada², Tadashi Ikehara² (1. GNF-J, 2. JAEA)

Time reserved for Chair (11:40 AM - 11:55 AM)

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