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Oral presentation

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

[2I12-15] Development of Analysis Method & Code 2

Tue. Mar 17, 2020 3:50 PM - 4:55 PM Room I (Lecture Bildg. M 2F M-23)

Chair:Hiroki Koike(MHI)

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3:50 PM - 4:05 PM

[2I12] BWR whole core nuclear-thermal hydraulic coupled simulation system

(6)Investigation of Assembly Discontinuity Factor correction method

*Masayuki Tojo¹, Michitaka Ono¹, Munenari Yamamoto (1. GNF-J)

4:05 PM - 4:20 PM

[2I13] An Investigation on Improvement of the Core Neutronics Design Calculation Method for Advanced Fast Reactors (6)

Investigation on the improvement in power distribution evaluation

*Kazuteru Sugino¹, Shigeo Ohki¹ (1. JAEA)

4:20 PM - 4:35 PM

[2I14] Improvement of Optimally-Weighted Predictor-Corrector Method for Nuclear Fuel Burnup Calculation (2)

*JUMPEI SASUGA¹, Go Chiba¹, Yasunori Ohoka², Kento Yamamoto², Hiroaki Nagano² (1. Hokkaido University, 2. NFI)

4:35 PM - 4:50 PM

[2I15] Extension of the hierarchical-domain decomposition boundary element method to the general multi-group diffusion equation

*Tian Qin¹, Go Chiba¹ (1. Hokkaido Univ)

Time reserved for Chair (4:50 PM - 4:55 PM)

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