Thermal-mechanical fatigue analysis of a main steam isolation valve of a boiling water reactor-5

I. Álvarez-Loya, J. A. Santillán-Gómez, C. J. Huesca-Damián, L. H. Hernández Gómez, J. A. Beltrán-Fernández, P. Ruiz-López

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

The Nuclear Steam Supply System (NSSS) of a Boiling Water Reactor (BWR) has been designed for directing and controlling the steam flow, from the reactor pressure vessel to the turbine. Furthermore, this system provides over-pressure protection for the Reactor Coolant System (RCS) and prevents fuel damage by restricting the loss of coolant in the reactor. In this paper, the fatigue and aging of a generic Main Steam Isolation Valve (MSIV) was analyzed. The body of such valve was evaluated. These conditions affect adversely the capacity and the functions of the valve. In the case, there is the risk of uncontrolled releases of radioactive particles to the external environment. The thermal fatigue analysis, which is reported, included three main thermal transients. They affect the NSSS system during its operating life. They are test of valve, shutdown of plant and turbine stop valve closure (TSV). All these evaluations were developed with a 3D CAD model in conjunction with the Finite Element Method. Finally, the remaining life and the allowable fatigue cycles were determined before the failure takes place. This work was based on the guidelines applicable to Nuclear Power Plants (NPP´s) contained in the ASME code.

Original languageEnglish
Title of host publicationProceedings of the 7th International Conference on Fracture Fatigue and Wear, FFW 2018
EditorsMagd Abdel Wahab
PublisherPleiades journals
Pages379-389
Number of pages11
ISBN (Print)9789811304101
DOIs
StatePublished - 2019
Event7th International Conference on Fracture Fatigue and Wear, FFW 2018 - Ghent, Belgium
Duration: 9 Jul 201810 Jul 2018

Publication series

NameLecture Notes in Mechanical Engineering
ISSN (Print)2195-4356
ISSN (Electronic)2195-4364

Conference

Conference7th International Conference on Fracture Fatigue and Wear, FFW 2018
Country/TerritoryBelgium
CityGhent
Period9/07/1810/07/18

Keywords

  • Aging
  • Cumulative Usage Factor
  • Damage
  • Nuclear Power Plant
  • Thermal transient stress

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