Oral presentation

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

[1M01-04] Uncertainty Evaluation 1

Wed. Sep 5, 2018 10:00 AM - 11:10 AM Room M (E11 -E Building)

Chair:Tomohiro Endo(Nagoya Univ.)

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10:00 AM - 10:15 AM

[1M01] Study on uncertainty propagation due to nuclear analysis codes on statistical safety evaluation method

(5) Influence of plant data uncertainty to static analysis

*Teppei Yamana¹, Hirohisa Kaneko¹, Yuji Honma¹, Kenichi Harada², Kohei Mochizuki³, rui kagiyama³, Takeshi Yamada³ (1. GNF-J, 2. Chubu Electric Power Co., Inc, 3. Hitachi GE)

10:15 AM - 10:30 AM

[1M02] Study on uncertainty propagation due to nuclear analysis codes on statistical safety evaluation method

(6) Influence of plant data uncertainty to dynamic analysis

*Kohei Mochizuki¹, Rui Kagiyama¹, Takeshi Yamada¹, Teppei Yamana², Yuji Honma², Hirohisa Kaneko², Kenichi Harada³ (1. Hitachi-GE, 2. GNF-J, 3. CHUBU Electric Power)

10:30 AM - 10:45 AM

[1M03] Proposal of efficient MCCV method using sensitivity evaluation result

*Shunsuke NIHIRA¹, Go Chiba¹ (1. Hokkaido Univ )

10:45 AM - 11:00 AM

[1M04] Investigation of uncertainty evaluation methodology for spent fuel pit due to nuclear data and manufacturing tolerances based on statistical approach

*Tetsuya Sugimura¹, Kazuki Kirimura¹, Hiroki Koike¹, Daisuke Sato¹, Toshikazu Takeda² (1. MHI, 2. Fukui Univ.)

Time reserved for Chair (11:00 AM - 11:10 AM)

Session information