Sensitivity analysis of nozzle geometry variables for estimating residual stress in rpv CRDM penetration nozzle

Hong Yeol Bae, Chang Young Oh, Yun Jae Kim, Kwon Hee Kim, Soo Won Chae, Ju Hee Kim

Research output: Contribution to journalArticle

1 Citation (Scopus)

Abstract

Recently, several circumferential cracks were found in the control rod drive mechanism (CRDM) nozzles of U.S. nuclear power plants. According to the accident analyses, coolant leaks were caused by primary water stress corrosion cracking (PWSCC). The tensile residual stresses caused by welding, corrosion sensitive materials, and boric acid solution cause PWSCC. Therefore, an exact estimation of the residual stress is important for reliable operation. In this study, finite element simulations were conducted to investigate the effects of the tube geometry (thickness and radius) on the residual stresses in a J-groove weld for different CRDM tube locations. Two different tube locations were considered (center-hole and steepest side hill tube), and the tube radius and thickness variables (ro/t=2, 3, 4) included two different reference values (ro=51.6, t=16.9mm).

Original languageEnglish
Pages (from-to)387-395
Number of pages9
JournalTransactions of the Korean Society of Mechanical Engineers, A
Volume37
Issue number3
DOIs
Publication statusPublished - 2013 Mar

Keywords

  • CRDM
  • FEA
  • PWSCC
  • RPV
  • Sensitivity Analysis

ASJC Scopus subject areas

  • Mechanical Engineering

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