摘要
核电厂安全壳极限抗压承载力、影响因素及其规律是核电结构安全评估、事故处理和结构设计的关键问题。本文以某安全壳为例,采用损伤塑性模型模拟混凝土的力学性能,双线形应力-应变模型模拟钢衬里和预应力钢束的材料非线性,基于ABAQUS软件系统地分析了核安全壳极限抗压承载力,并给出了结构自重、预应力、钢衬里等因素的影响规律。研究表明,当内压增大到0.87 MPa时,安全壳筒壁上部混凝土开始进入塑性;当内压增大到1.02 MPa时,钢衬里最大拉应变超过限值3 000×10-6,安全壳达到极限状态。在各种影响因素中,预应力和钢衬里对安全壳的极限内压和破坏形式起着关键作用。本文研究结果对核安全壳极限承载能力分析、结构设计和安全评定等方面具有一定的参考价值。
Ultimate compressive bearing capacity, influenced factors and its rules of nuclear RC containment are key problems of safety assessment, accident treatment and structure design, etc. Ultimate compressive bearing capacity of nuclear RC containment is shown by concrete damaged plasticity model and steel double liner model of ABAQUS. The study shows that the concrete of nuclear RC containment cylinder wall becomes plastic when the internal pressure is up to 0.87 MPa, the maximum tensile strain of steel liner exceeds 3000 X 106 and nuclear RC containment reaches ultimate status when the internal pressure is up to 1.02 MPa. The result shows that nuclear RC containment is in elastic condition under the design internal pressure and the bearing capacity meets requirement. Prestress and steel liner play key parts in the ultimate internal pressure and failure mode of nuclear RC containment. The study results have value for the analysis of ultimate compressive bearing capacity, structure design and safety assessment.
出处
《核科学与工程》
CAS
CSCD
北大核心
2014年第2期228-235,共8页
Nuclear Science and Engineering
基金
中央高校基本科研业务费专项资金项目:核电结构抗震试验和数值仿真研究(HEUCFZ1127)
关键词
核安全壳
极限承载力
影响因素
ABAQUS
nuclear RC containment
ultimate bearing capacity
influencingfactors
ABAQUS
