Oral presentation

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

[2G05-09] Analysis Method Development 1

Thu. Sep 14, 2017 10:35 AM - 11:55 AM Room G (C213 - C Block)

Chair:Kazuki Kirimura (MHI)

+Add all to schedule

10:35 AM - 10:50 AM

[2G05] Supercritical transient analysis in hypothetical fuel debris by multi-region approach based on integral kinetic model

*Delgersaikhan Tuya¹, Toru Obara² (1. Department of Nuclear Engineering, Tokyo Institute of Technology, 2. Laboratory for Advanced Nuclear Energy, Institute of Innovative Research, Tokyo Institute of Technology)

10:50 AM - 11:05 AM

[2G06] Nuclear reactor one-point kinetic calculations with explicit model of fission product nuclides

*Koji Katagiri¹, Go Chiba¹, Tadashi Narabayashi¹ (1. Hokkaido Univ.)

11:05 AM - 11:20 AM

[2G07] Analysis of ICPP criticality accident by Quasi-steady-state method taking into account change in uranium concentration during boiling

*Tomoaki Watanabe¹, Yuichi Yamane¹ (1. Japan Atomic Energy Agency)

11:20 AM - 11:35 AM

[2G08] Investigation of burnup calculations using Optimally-Weighted Predictor Corrector Method

*Shintaro Okumura¹, Go Chiba¹, Tadashi Narabayashi¹ (1. Hokkaido Univercity)

11:35 AM - 11:50 AM

[2G09] An Investigation of the Core Neutronics Analysis Conditions for Evaluation of Burnup Nuclear Characteristics of Next-Generation Fast Reactors

(2)The Core Neutronics Analysis Conditions for Evaluation of Fuel Assembly Power Distribution and Maximum Linear Power Density

*Kazuo Takino¹, Kazuteru Sugino¹, Shigeo Ohki¹ (1. JAEA)

Time reserved for Chair (11:50 AM - 11:55 AM)

Session information