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When the length of the TWC is smaller than the initial length, the leakage of the TWC is not detected by non-destructive examination (NDE), the leakage detective system or other checking ways (such as the daily round check). A Fatigue-Crack Propagation Analysis Program and Its Application 25 (b) The variation (transient) of the temperature and the pressure of the primary coolant leads to the stress variation and fatigue propagation of the TWC. The influences of other failure mechanisms (such as stress corrosion crack) are not considered.
17. Gao Yongjun, “Reduction of Limiters and Dampers and the Stress Analysis for the Primary Circuit of CPR1000 NPP” (in Chinese), internal report of Suzhou Nuclear Power Institute, June 2009. , in Suzhou Nuclear Power Institute (SNPI) from 2005 till now. A Study on the Tensile Properties of Materials at Elevated Temperature in RCC-M Lifeng Guo, Yuxin Wang and Zhe Li Abstract The tensile properties of materials at elevated temperature shall be ensured for PWR (pressurized water reactor) nuclear components as the components normally are used in elevated temperature applications.
V. Smith some decades ago. When the RCC-M grade has no equivalent in the ASME BPVC, the values of speciﬁed minimum yield strength at elevated temperature given in the NFA or EN standards were chosen as values of Sy. The value of Su was taken equal to the speciﬁed Rm value at room temperature, until this value reaches 110% of the tensile strength value given in the standard . An example is RCC-M M1131 P265GH carbon plate, which is widely used for fabrication of classes 2 and 3 components. 2 at temperature in EN standard for 40 < t ≤ 60 mm.