反應(yīng)堆堆芯圍筒結(jié)構(gòu)熱流固耦合熱變形分析 反應(yīng)堆堆芯

反應(yīng)堆堆芯圍筒結(jié)構(gòu)熱流固耦合熱變形分析 反應(yīng)堆堆芯 摘要： 針對反應(yīng)堆堆芯圍筒熱流固耦合問題，采用三維有限元法研究堆芯圍筒的熱變形.考察ANSYS的三維實(shí)體熱單元SOLID 70，三維實(shí)體單元SOLID 45，三維表面熱效應(yīng)單元SURF 152和三維熱流耦合管單元FLUID 116等單元類型的特點(diǎn)和實(shí)用性.建立堆芯圍筒、吊籃和冷卻劑的溫度分析有限元模型：堆芯圍筒和吊籃采用SOLID 70，結(jié)構(gòu)表面與冷卻劑的對流傳熱表面采用SURF 152，堆芯圍筒與吊籃之間冷卻劑采用FLUID 116.采用SOLID 45建立堆芯圍筒有限元模型，根據(jù)得到的堆芯圍筒、吊籃和冷卻劑的溫度場結(jié)果分析堆芯圍筒熱變形.結(jié)果表明，在考慮堆芯圍筒及吊籃固體和流體的交叉耦合的基礎(chǔ)上，采用三維有限元法能比較客觀地模擬反應(yīng)堆堆芯處的復(fù)雜運(yùn)行環(huán)境. 關(guān)鍵詞： 反應(yīng)堆； 堆芯圍筒； 熱變形分析； 熱流固耦合； 冷卻劑； ANSYS ： TL351.1 文獻(xiàn)標(biāo)志碼： B Thermal deformation analysis on thermalfluidstructure coupling of reactor core shroud ZHAO Feiyun, ZHU Kun, LI Yuan, YU Hao, WENG Yu, ZHANG Ming (Shanghai Nuclear Engineering Research & Design Institute, Shanghai xx33, China) Abstract： As to the thermalfluidstructure coupling issue of reactor core shroud, the thermal deformation of core shroud is researched by 3D finite element method. The characteristics and practicability are researched for ANSYS element types including 3D solid thermal element SOLID 70，3D solid element SOLID 45，3D surface thermal effect element SURF 152 and 3D thermalfluid coupling pipe element FLUID 116. The finite element models of thermal analysis are built for reactor core shroud, barrel and coolant. For the models, the core shroud and barrel are modeled by SOLID 70; the structure surface and convective heat transfer surface of coolant are modeled by SURF 152; the coolant between core shroud and barrel is modeled by FLUID 116. The finite element model of thermal deformation analysis is built for core shroud by SOLID 45, and the thermal deformation of core shroud is analyzed aording to the temperature field results of core shroud, barrel and coolant. The results indicate that, considering the thermalfluidstructure coupling among core shroud, barrel and coolant, the plex running environment of reactor core shroud can be simulated objectively by 3D finite element method. Key words： reactor; core shroud; thermal deformation analysis; thermalfluidstructure coupling; coolant; ANSYS 0 引 言 CAE逐漸成為工程應(yīng)用的主要工具1,在我國核電廠主設(shè)備的結(jié)構(gòu)和熱工水力分析中，CAE分析技術(shù)已成為關(guān)鍵工具之一2.反應(yīng)堆堆內(nèi)構(gòu)件由堆芯圍筒、吊籃、堆芯支撐板等部件組成，是核電廠主設(shè)備中的關(guān)鍵核島設(shè)備.作為堆內(nèi)構(gòu)件的重要部分之一，圍筒構(gòu)成堆芯的徑向邊界，控制流經(jīng)堆芯的冷卻劑方向和流量，起到從圓形吊籃向方形燃料組件構(gòu)件的堆芯邊界的過渡作用.34 對于反應(yīng)堆堆芯的圍筒結(jié)構(gòu)熱流固耦合問題，通常采用簡化的一維導(dǎo)熱模型計(jì)算需要考察的局部溫度和熱變形等.5姜乃斌等6采用三維有限元法計(jì)算堆內(nèi)構(gòu)件等主設(shè)備，實(shí)現(xiàn)在現(xiàn)有計(jì)算機(jī)硬件條件下的整體大規(guī)模三維有限元分析，但未對堆芯圍筒及吊籃結(jié)構(gòu)進(jìn)行具體的熱變形計(jì)算分析. 本文以反應(yīng)堆堆芯圍筒結(jié)構(gòu)為主要研究對象，針對堆芯圍筒及吊籃結(jié)構(gòu)的流固耦合問題7，建立有限元分析模型，分析研究堆芯圍筒的熱變形，考察ANS