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首页> 外文期刊>Strength of Materials >EVALUATION OF THERMOCYCLIC LOADS IN THE WELDING UNIT OF THE 'HOT' COLLECTOR AND THE BRANCH PIPE OF THE PGV-1000 STEAM GENERATOR
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EVALUATION OF THERMOCYCLIC LOADS IN THE WELDING UNIT OF THE 'HOT' COLLECTOR AND THE BRANCH PIPE OF THE PGV-1000 STEAM GENERATOR

机译:PGV-1000蒸汽发生器的“热”集电极和支管焊接单元中的热负荷的评估

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摘要

Safe operation of nuclear power plants is impossible without providing strength of their equipment and pipelines in view of their equipment and pipelines in view of real loading conditions. In this context, it becomes clear why each case of initiation of crack-type damages in pieces of equipment presents significant interest for experts in the field of strength of materials. During operation within the design service life, cracks were detected in the welding unit of the "hot" collector and the branch pipe of the PGV-l000 steam generator of a nuclear power plant with a VVER-l000 reactor. The investigations performed in this connection failed to reveal the cause of damage initiation All the discovered damages (cracks) were located practically in the same place of the welding units of the "hot" collector and the branch pipe, which, in this case, indicates the presence of a common factor of loading that acts in the unit and was not considered in strength calculations earlier.
机译:鉴于实际负载条件,如果不提供核电厂的设备和管道的强度,就不可能确保核电厂的安全运行。在这种情况下,很清楚的是,为什么在设备部件中引发裂纹类型损坏的每种情况都引起了材料强度领域的专家的极大兴趣。在设计使用寿命内运行期间,在带有VVER-1000反应堆的核电厂的“热”集热器的焊接单元和​​PGV-1000蒸汽发生器的支管中检测到裂纹。在这方面进行的调查未能揭示造成损坏的原因。所有发现的损坏(裂纹)实际上都位于“热”集热器和支管焊接单元的同一位置,在这种情况下,表明存在作用在单元中的公共载荷因子,并且在早期的强度计算中并未考虑。

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