Accumulated Damage of the Main Steam Nozzle of a BWR-5-Reference-Cited by-同舟云学术

Accumulated Damage of the Main Steam Nozzle of a BWR-5

Published:2023 Issue: Volume: Page:305-315
ISSN:1869-8433
Container-title:Advanced Structured Materials
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Author:

Arreola-Valles Tanya Nerina,Hernández-Gómez Luis Héctor,Armenta-Molina Alejandra,Pérez-Montejo Salatiel,Ramos-Cantú Lenin,Moctezuma-Reyes José Javier,Álvarez-Loya Irving

Publisher

Springer Nature Switzerland

Link

https://link.springer.com/content/pdf/10.1007/978-3-031-26466-5_20

Reference13 articles.

1. Alvarez-Loya I, López-Grijalba Y,Carbajal-Figueroa LG, Hernández-Gómez LH, Ruiz-López P, Beltrán-Fernández JA (2019) Lineal elastic fracture mechanics analysis applied for the evaluation of the structural integrity of a boiling water reactor vessel considering neutronic irradiation. Defect Diffus Forum. https://doi.org/10.4028//DDF.390.151

2. Carbajal-Figueroa LG, Pérez-Montejo S, Armenta-Molina A, Soto-Mendoza G, Hernández-Gómez LH, Beltrán-Fernández JA, Ruiz-López P (2020) Environmental fatigue analysis of the feedwater piping system of a BWR-5. Adv Structured Mater. https://doi.org/10.1007/978-3-030-39062-4_7

3. Chou HW, Shen YY, Huang CC (2018) Comparison of pressure-temperature limits for a pressurized water reactor pressure vessel considering beltline and extended beltline regions. Press Vessels Pip Conf. https://doi.org/10.1115/PVP2018-84145

4. GE Nuclear Energy (1980) BWR/6 General description of a boiling water reactor

5. Liu R, Huang M, Peng Y, Wen HY, Huang JJ, Ruan CH, Ma HS, Li Q (2018) Analysis for crack growth regularities in the nozzle-cylinder intersection area of reactor pressure vessel. Ann Nucl Energy. https://doi.org/10.1016/j.anucene.2017.10.021