2016年春の年会

講演情報

一般セッション

III. 核分裂工学 » 304-1. 伝熱・流動(エネルギー変換・輸送・貯蔵を含む)

[2C06-10] 福島原発事故関連2

2016年3月27日(日) 10:50 〜 12:10 C会場 (講義棟B棟 B103)

座長:溝上 伸也(東京電力)

10:50 〜 11:05

[2C06] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(64)Validation of SAMPSON/DCA creep model against OLHF experiments

*Filippo Scarpa1, Marco Pellegrini1, Masanori Naitoh1 (1.IAE)

キーワード:SAMPSON, OLHF, Lower Head Failure, Severe Accident

Time to failure prediction of RPV lower head is very important in severe accident analysis. Mechanical creep failure of the lower head was studied in OLHF experiments with high temperature difference across vessel wall and different internal pressure (12.3 MPa and 5 MPa). For the validation of the SAMPSON/DCA module two creep models are implemented based on two different failure criteria: damage function and failure by deformation respectively.