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AN ANALYTICAL MODEL FOR SHEAR STRENGTH OF END SLABS OF PRESTRESSED CONCRETE NUCLEAR REACTOR VESSELS

机译:预应力混凝土核反应堆容器端板抗剪强度的解析模型

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The object of this investigation was the development of a method to permit reliable calculation of the strength of end slabs of prestressed concrete nuclear reactor vessels.nThe experimental study included the tests to failure under internal pressure of ten small-scale cylindrical vessels with flat end slabs. The vessels were prestressed circumferentially and longitudinally. The end slab had no additional reinforcement.nThe experimental variables were the end-slab thickness, size and arrangement of penetrations in the end slab, and the concrete strength. The penetrations, which were not reinforced by sleeves or liners, were closed by steel plates at the pressurized surface of the slabs (Fig. 1.1).

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