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国内核安全有关混凝土结构设计规范尚未形成完善的体系,多数核电厂参照美国ACI规范或欧标规范进行结构设计。基于CAP1000及CAP1400核电厂结构设计,对比研究了美国(ACI 349)《核安全有关混凝土结构设计规范》与中国(GB 50010)《混凝土结构设计规范》及(NB/T20012)《压水堆核电厂核安全有关的混凝土结构设计要求》在混凝土构件承载力设计上的异同,并就构件抗压、抗弯、抗剪、抗拉等的安全裕度进行了对比。研究表明:中美规范在构件抗压、抗拉、纯弯及拉弯设计中承载力安全裕度基本相当,但在构件抗剪、压弯设计中,按GB 50010及NB/T20012设计的承载力安全裕度低于ACI 349规范,故提出了调整建议。
The national nuclear safety related concrete structure design specification has not formed the perfect system, most nuclear power plants refer to the American ACI standard or the European standard specification to carry on the structural design. Based on the structural design of CAP1000 and CAP1400 nuclear power plants, the comparison between ACI 349 “Code for Design of Nuclear Safety Concrete Structures” and China (GB 50010) “Code for Design of Concrete Structures” and (NB / T20012) “PWR Nuclear Power Plant Nuclear safety related to the design requirements of concrete structures, ”the similarities and differences in the design of bearing capacity of concrete members, and components of compression, bending, shear, tensile and other safety margin compared. The results show that the safety margin of bearing capacity is basically the same in the design of compression, tensile, pure bending and bending of components in China-US Code. However, in the design of shear resistance and buckling of components, the load bearing designed according to GB 50010 and NB / T20012 Force safety margin is lower than the ACI 349 specification, so adjust the recommendations.