CAJ | 학술논문

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 MP a 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3000×10-6,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。
핵전엄안전각겁한항압승재력、영향인소급기규률시핵전결구안전평고、사고처리화결구설계적관건문제。본문이모안전각위례,채용손상소성모형모의혼응토적역학성능,쌍선형응력-응변모형모의강츤리화예응력강속적재료비선성,기우 ABAQUS연건계통지분석료핵안전각겁한항압승재력,병급출료결구자중、예응력、강츤리등인소적영향규률。연구표명,당내압증대도0??87 MP a 시,안전각통벽상부혼응토개시진입소성；당내압증대도1??02 MPa시,강츤리최대랍응변초과한치3000×10-6,안전각체도겁한상태。재각충영향인소중,예응력화강츤리대안전각적겁한내압화파배형식기착관건작용。본문연구결과대핵안전각겁한승재능력분석、결구설계화안전평정등방면구유일정적삼고개치。
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 × 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.