Nuclear safety related concrete structures have inherently large margin of capacity between the ultimate and serviceability limit state, mainly due to the requirement to remain essentially elastic in the event of a design basis earthquake. Despite this, cracking can occur from either direct loading, restraint or imposed deformations, including early-age thermal cracks due to temperature differential or externally restrained thermal strain. This paper presents an overview of current UK practice for control of cracks in nuclear safety-related concrete structures and provides a discussion of the provisions of ACI 349-13, ASME BPVC 2013 Section III, Division 2 (ACI 359-13), the European Pressurised Reactor Technical Code for Civil Works (ETC-C) and Eurocode 2 (BS EN 1992). This is followed by recommendations for design.
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机译:核安全相关的混凝土结构本质上具有较大和可维护性极限状态之间的容量幅度,主要是由于要求在设计基地发生基本上仍然弹性。尽管如此,裂缝可能从直接加载,约束或施加的变形发生,包括由于温差或外部受限制的热应变引起的早期热裂缝。本文概述了当前英国核心安全相关混凝土结构控制裂缝的实践,并讨论了ACI 349-13,ASME BPVC 2013第三节,第2款(ACI 359-13),欧洲民用工程(ETC-C)和EUROCODE 2(BS EN 1992)的加压反应堆技术守则。这是设计建议。
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