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（中廣核工程有限公司， 深圳 518124）

［摘要］基于軟件ABAQUS，對(duì)核電站典型結(jié)構(gòu)模塊中的特殊結(jié)構(gòu)節(jié)點(diǎn)——鋼板混凝土墻體與鋼筋混凝土基礎(chǔ)底板連接部位進(jìn)行不同工況下的數(shù)值分析。在有限元模型中，混凝土采用塑性損傷模型，鋼板采用塑性硬化模型，得出了不同工況下的破壞形態(tài)和極限承載力，并針對(duì)相應(yīng)的工況對(duì)比美國(guó)規(guī)范ANSI/AISC-N690和日本規(guī)范JEAG-4618。結(jié)果表明：美國(guó)規(guī)范ANSI/AISC-N690在計(jì)算構(gòu)件的平面內(nèi)抗剪、平面外抗剪及抗彎強(qiáng)度時(shí)，計(jì)算結(jié)果比日本規(guī)范JEAG-4618保守；埋入式錨固節(jié)點(diǎn)的承載力要略優(yōu)于插筋式錨固節(jié)點(diǎn)的承載力。

［關(guān)鍵詞］核電站； 鋼板混凝土墻體； ABAQUS

中圖分類號(hào)：TU398+.9文獻(xiàn)標(biāo)識(shí)碼：A文章編號(hào)：1002-848X(2018)16-0065-07

Analysis on bearing capacity of connection between steel-concrete wall and reinforced concrete base mat

Xu Zhengyu, Li Zhongcheng, Chen Yi, Xu Haitao

(China Nuclear Power Engineering Co.,  Ltd.,  Shenzhen 518124, China)

Abstract:Base on the ABAQUS software, the numerical analysis of  connection between  steel-concrete(SC) wall and reinforced concrete base mat of the typical structural module of the nuclear power plants was carried out. The concrete with the plastic damage material and the steel with the kinematic hardening rule were considered in finite element model. The failure modes and the ultimate bearing capacity under different load cases were obtained. The difference  under the relevant load case  between  American code ANSI/AISC-N690 and Japanese code JEAG-4618  was compared as well. The results show that, the strength values of the in-plane shear, out-plane shear and the flexural from  American code ANSI/AISC-N690 are more conservative than those from Japanese code JEAG-4618, in addition the performance of the embedment anchoring connection joint is better than the reinforcement anchoring connection joint.

Keywords:nuclear power plant; steel-concrete wall; ABAQUS

作者簡(jiǎn)介：徐征宇，碩士，高級(jí)工程師，Email:xuzhengyu@cgnpc.com.cn。