PSI - Issue 17

Salatiel Pérez Montejo et al. / Procedia Structural Integrity 17 (2019) 123–130 Salatiel Pérez Montejo et al/ Structural Integrity Procedia 00 (2019) 000 – 000

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calculated with the ASME code procedure is 232 ° F. On the other hand, T equals 185 ° F, when it is evaluated numerically for the start-up transient and 187 ° F for the shut down-cooled transient. the results vary approximately 25%. If the temperature-pressure limits are calculated with a numerical method like FEM, the limits are not as restrictive as traditional-analytical approach. The operating range of a nuclear reactor is wider. Fig. 5d shows that SIF is maximum at the deepest point of the crack. In this case, the crack would propagate across the thickness. It is important to observe, the results envelope the conditions that could take place during 60 years of operation or extended power uprates. Acknowledgements The authors kindly acknowledge the grant for the development of the Project 211704. It was awarded by the National Council of Science and Technology (CONACyT) of Mexico.

Statement

The conclusions and opinions stated in this paper do not represent the position of the National Commission on Nuclear Safety and Safeguards, where the co-author Pablo Ruiz López is working as an employee. Although special care has been taken to maintain the accuracy of the information and results, all the authors do not assume any responsibility for the consequences of its use. The use of particular mentions of countries, territories, companies, associations, products or methodologies does not imply any judgment or promotion by all the authors.

References

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