原子能科学技术
原子能科學技術
원자능과학기술
ATOMIC ENERGY SCIENCE AND TECHNOLOGY
2009年
z2期
271-274
,共4页
张丽%何树延%吴莘馨%刘俊杰
張麗%何樹延%吳莘馨%劉俊傑
장려%하수연%오신형%류준걸
高温气冷堆%热气导管%结构强度%有限元计算
高溫氣冷堆%熱氣導管%結構彊度%有限元計算
고온기랭퇴%열기도관%결구강도%유한원계산
high-temperature gas-cooled reactor%hot gas duct%structure strength%finite element analysis
500 MW高温气冷堆示范电站(HTR-PM)的反应堆压力容器与蒸汽发生器通过热气导管连接,热气导管是反应堆堆芯出口氦气导入蒸汽发生器的主要通道.热气导管是安全三级、抗震Ⅰ类部件,根据ASME规范,要求热气导管能在地震条件下保持结构的完整性.为验证热气导管在反应堆寿期内的安全可靠性,本文建立了热气导管有限元计算模型,计算了热气导管在绝热纤维压力、压力边界失压的压差、自重以及地震载荷等多种载荷作用下,内衬管、锥管与外管的应力分布状况.计算结果表明,热气导管各部分强度有较大裕度,可承受运行载荷、失压载荷以及地震载荷.
500 MW高溫氣冷堆示範電站(HTR-PM)的反應堆壓力容器與蒸汽髮生器通過熱氣導管連接,熱氣導管是反應堆堆芯齣口氦氣導入蒸汽髮生器的主要通道.熱氣導管是安全三級、抗震Ⅰ類部件,根據ASME規範,要求熱氣導管能在地震條件下保持結構的完整性.為驗證熱氣導管在反應堆壽期內的安全可靠性,本文建立瞭熱氣導管有限元計算模型,計算瞭熱氣導管在絕熱纖維壓力、壓力邊界失壓的壓差、自重以及地震載荷等多種載荷作用下,內襯管、錐管與外管的應力分佈狀況.計算結果錶明,熱氣導管各部分彊度有較大裕度,可承受運行載荷、失壓載荷以及地震載荷.
500 MW고온기랭퇴시범전참(HTR-PM)적반응퇴압력용기여증기발생기통과열기도관련접,열기도관시반응퇴퇴심출구양기도입증기발생기적주요통도.열기도관시안전삼급、항진Ⅰ류부건,근거ASME규범,요구열기도관능재지진조건하보지결구적완정성.위험증열기도관재반응퇴수기내적안전가고성,본문건립료열기도관유한원계산모형,계산료열기도관재절열섬유압력、압력변계실압적압차、자중이급지진재하등다충재하작용하,내츤관、추관여외관적응력분포상황.계산결과표명,열기도관각부분강도유교대유도,가승수운행재하、실압재하이급지진재하.
The hot gas duct of China 500 MW Pilot High-Temperature Gas-cooled Reactor connects the reactor pressure vessel and the steam generator. The hot gas duct is the main passage of the helium from the reactor core to the steam generator. The hot gas duct is class 3 component in nuclear security standard. According to ASME criterion, it is required that the hot gas duct should keep its integrality during the seism. In order to validate the reliability, the finite element analysis model of the hot gas duct was established and the stress distribution was calculated with the load of the pressure of the insulation fiber, the differential pressure, the gravity and the seism. The calculation shows that the structure strength of the hot gas duct has a large safety margin under the operation load, loss of pressure and seism load.