*masato uchita¹, Takayuki Miyagawa¹, Masao Eto², Suzuno Tetsuji², Sigenobu Kubo³, Yoshitaka Chikazawa³ (1. Japan Atomic Power Company , 2. Mitsubishi FBR Systems Inc., 3. Japan Atomic Energy Agency)

5:10 PM - 5:25 PM

[2O19] A Conceptual Design Study on Pool-type Sodium-cooled Fast Reactor with Enhanced Anti-seismic Capability

(2)A Study on Safety Design Concept

*Shigenobu Kubo¹, Koichi Higurashi³, Takayuki Miyagawa² (1. JAEA, 2. JAPC, 3. MFBR)

5:25 PM - 5:40 PM

[2O20] A Conceptual Design Study on Pool-type Sodium-cooled Fast Reactor with Enhanced Anti-seismic Capability

(3) Steady State Thermal Hydraulic Analyses in Reactor Vessel

*Ichiyo Matoba¹, Junji Endo¹, Osamu Watanabe¹, Yoshitaka Chikazawa², Shigenobu Kubo², Hiroyuki Ohshima², Masato Uchita³ (1. Mitsubishi FBR Systems Inc., 2. Japan Atomic Energy Agency, 3. Japan Atomic Power Company)

Time reserved for Chair （5:40 PM - 5:45 PM）

Sessions

IV. Nuclear Plant Technologies » 401-3 Reactor Design, Construction and Examination of Nuclear Power Station, Aseismatic Design, Nuclear Ship

[2O12-15] Design and Inspection of LWRs

[2O12] The AP1000® Plant Startup Test Program

(1) Pre-Fuel Load

[2O13] The AP1000® Plant Startup Test Program

(2) Fuel Load

[2O14] Evaluation of sloshing wave crest impact pressure acting on a fixed roof cylindrical tank

(1)Validation of numerical models and applicability of estimation methods of Slosh-induced impact pressure

[2O15] Research on extent of examination in non-destructive inspection based on probabilistic fracture mechanics

[2O16-20] Design and Demand of Advanced Reactor

[2O16] Potential of SMR in various power markets

[2O17] Fragility Evaluation of the Reactor Vessel of Fast Reactor using Inelastic Analysis

[2O18] A Conceptual Design Study on Pool-type Sodium-cooled Fast Reactor with Enhanced Anti-seismic Capability