Lineal elastic fracture mechanics analysis applied for the evaluation of the structural integrity of a boiling water reactor vessel considering neutronic irradiation

Irving Alvarez-Loya, Yunuén López-Grijalba, Laura G. Carbajal-Figueroa, Luis H. Hernández-Gómez, Pablo Ruiz-López, Juan A. Beltrán-Fernández

Research output: Contribution to journalArticleResearchpeer-review

Abstract

© 2019 Trans Tech Publications, Switzerland This paper shows the methodology used for the evaluation of the structural integrity of a boiling water reactor (BWR-5). This evaluation is relevant, because this vessel is the coolant pressure boundary for cooling the nuclear core. In the case of this paper, an axial crack is postulated in the adjacent internal wall of a vessel to the core, which is denominated beltline. Such a crack is subjected to an internal pressure and neutron irradiation. Additionally, a crack on the inlet nozzle of the low-pressure coolant injection (LPCI) was also considered. The analysis presented in this paper, evaluated the transient conditions which take place during the start-up and shutdown of a BWR 5. The neutronic irradiation damage at the beltline was also incorporated to the analysis. It induces an embrittlement. Linear elastic fracture mechanics was applied with the requirements established at the Appendix G of ASME Code Section XI. The finite element method was used to simulate the transient conditions of the components considering the critical parameter, such as the service temperature, thickness, stresses and the material properties.
Original languageAmerican English
Pages (from-to)151-160
Number of pages134
JournalDefect and Diffusion Forum
DOIs
StatePublished - 1 Jan 2019

Fingerprint

boiling water reactors
Boiling water reactors
fracture mechanics
Structural integrity
Fracture mechanics
integrity
vessels
cracks
Irradiation
coolants
Cracks
Coolants
irradiation
evaluation
inlet nozzles
shutdowns
embrittlement
internal pressure
Neutron irradiation
neutron irradiation

Cite this

@article{d8c3e8f1128648c29761e51466301456,
title = "Lineal elastic fracture mechanics analysis applied for the evaluation of the structural integrity of a boiling water reactor vessel considering neutronic irradiation",
abstract = "{\circledC} 2019 Trans Tech Publications, Switzerland This paper shows the methodology used for the evaluation of the structural integrity of a boiling water reactor (BWR-5). This evaluation is relevant, because this vessel is the coolant pressure boundary for cooling the nuclear core. In the case of this paper, an axial crack is postulated in the adjacent internal wall of a vessel to the core, which is denominated beltline. Such a crack is subjected to an internal pressure and neutron irradiation. Additionally, a crack on the inlet nozzle of the low-pressure coolant injection (LPCI) was also considered. The analysis presented in this paper, evaluated the transient conditions which take place during the start-up and shutdown of a BWR 5. The neutronic irradiation damage at the beltline was also incorporated to the analysis. It induces an embrittlement. Linear elastic fracture mechanics was applied with the requirements established at the Appendix G of ASME Code Section XI. The finite element method was used to simulate the transient conditions of the components considering the critical parameter, such as the service temperature, thickness, stresses and the material properties.",
author = "Irving Alvarez-Loya and Yunu{\'e}n L{\'o}pez-Grijalba and Carbajal-Figueroa, {Laura G.} and Hern{\'a}ndez-G{\'o}mez, {Luis H.} and Pablo Ruiz-L{\'o}pez and Beltr{\'a}n-Fern{\'a}ndez, {Juan A.}",
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Lineal elastic fracture mechanics analysis applied for the evaluation of the structural integrity of a boiling water reactor vessel considering neutronic irradiation. / Alvarez-Loya, Irving; López-Grijalba, Yunuén; Carbajal-Figueroa, Laura G.; Hernández-Gómez, Luis H.; Ruiz-López, Pablo; Beltrán-Fernández, Juan A.

In: Defect and Diffusion Forum, 01.01.2019, p. 151-160.

Research output: Contribution to journalArticleResearchpeer-review

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AU - Hernández-Gómez, Luis H.

AU - Ruiz-López, Pablo

AU - Beltrán-Fernández, Juan A.

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N2 - © 2019 Trans Tech Publications, Switzerland This paper shows the methodology used for the evaluation of the structural integrity of a boiling water reactor (BWR-5). This evaluation is relevant, because this vessel is the coolant pressure boundary for cooling the nuclear core. In the case of this paper, an axial crack is postulated in the adjacent internal wall of a vessel to the core, which is denominated beltline. Such a crack is subjected to an internal pressure and neutron irradiation. Additionally, a crack on the inlet nozzle of the low-pressure coolant injection (LPCI) was also considered. The analysis presented in this paper, evaluated the transient conditions which take place during the start-up and shutdown of a BWR 5. The neutronic irradiation damage at the beltline was also incorporated to the analysis. It induces an embrittlement. Linear elastic fracture mechanics was applied with the requirements established at the Appendix G of ASME Code Section XI. The finite element method was used to simulate the transient conditions of the components considering the critical parameter, such as the service temperature, thickness, stresses and the material properties.

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