Oral presentation

[3K04-07] Evaluation Technology and Plant Safety Assessment

Wed. Mar 28, 2018 10:55 AM - 12:00 PM Room K (U3-311 -U3 Building)

Chair: Noritoshi Minami (CRIEPI)

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10:55 AM - 11:10 AM

[3K04] Comparison of calculation results between KENO and MCNP codes as for irregular rod pitch in cask model

*Hiroshi Unehara¹, Hironori Mizobuchi¹, Naotsugu Kikuchi¹, Masayuki Kanno¹, Naoto Kubota¹ (1. OCL Corporation)

11:10 AM - 11:25 AM

[3K05] Failure risk evaluation of acceptance criteria for Japanese RPV integrity evaluation method against pressurized thermal shock events

*Takeshi Murakami¹, Takatoshi Hirota¹, Kenichi Nakashima² (1. Mitsubishi Heavy Industries, LTD., 2. Cenral Research Institute of Electric Power Industry)

11:25 AM - 11:40 AM

[3K06] Effect of repressurization on integrity evaluation of reactor pressure vessel using probabilistic fracture mechanics

*Takashi Suzuki¹, Masahide Suzuki¹, Kenta Murakami¹, Jinya Katsuyama², Yinsheng Li² (1. Nagaoka University of Technology, 2. Japan Atomic Energy Agency)

11:40 AM - 11:55 AM

[3K07] AP1000^® safety assessment for beyond design basis events

(3)Containment Integrity

*Yukitaka Yamazaki¹, James H Scobel², Richard F Wright² (1. Westinghouse Electric Japan Ltd., 2. Westinghouse Electric Company)

Time reserved for Chair （11:55 AM - 12:00 PM）

Sessions

III. Fission Energy Engineering » 305-3 Reactor Design, Construction and Examination of Nuclear Power Station, Aseismatic Design, Nuclear Ship

[3K04-07] Evaluation Technology and Plant Safety Assessment

[3K04] Comparison of calculation results between KENO and MCNP codes as for irregular rod pitch in cask model

[3K05] Failure risk evaluation of acceptance criteria for Japanese RPV integrity evaluation method against pressurized thermal shock events

[3K06] Effect of repressurization on integrity evaluation of reactor pressure vessel using probabilistic fracture mechanics

[3K07] AP1000^® safety assessment for beyond design basis events

(3)Containment Integrity

Authentication

Sessions

III. Fission Energy Engineering » 305-3 Reactor Design, Construction and Examination of Nuclear Power Station, Aseismatic Design, Nuclear Ship

[3K04-07] Evaluation Technology and Plant Safety Assessment

[3K04] Comparison of calculation results between KENO and MCNP codes as for irregular rod pitch in cask model

[3K05] Failure risk evaluation of acceptance criteria for Japanese RPV integrity evaluation method against pressurized thermal shock events

[3K06] Effect of repressurization on integrity evaluation of reactor pressure vessel using probabilistic fracture mechanics

[3K07] AP1000® safety assessment for beyond design basis events

(3)Containment Integrity

Authentication

[3K07] AP1000^® safety assessment for beyond design basis events