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)

11:50 〜 12:05

[2C10] Assessment of Core Status of TEPCO's Fukushima Daiichi Nuclear Power Plants

(68)A new heat transfer model for simulating Corium-Concrete Interaction in DSA module of SAMPSON code

*Mirco Giuli1, Marco Pellegrini1, Masanori Naitoh1 (1.IAE The institute of Applied Energy)

キーワード:Severe Accident scenario, MCCI, SAMPSON code, Heat Transfer Mechanism

One of the major issues raised by molten corium concrete interaction (MCCI) is how the 2D cavity ablation in an oxidic pool evolves. In order to reproduce the different ablation behavior observed for limestone and siliceous concrete during CCI-2 and CCI-3 experiments, a new heat transfer correlation was implemented in the DSA module. The new model was develop by T. Sevòn and takes into account heat conduction and gas release in and from the concrete for calculating the heat transfer coefficient (HTC). Three correlation for the bubbling-enhanced HTC were implemented. For the basemat, a single correlation can be used for siliceous and limestone concrete. For the sidewall, two different correlation are needed, for the two concrete types.