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

doi:10.3795/KSME-A.2013.37.3.387

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

School of Mechanical Engineering

Research output: Contribution to journal › Article › peer-review

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 language	English
Pages (from-to)	387-395
Number of pages	9
Journal	Transactions of the Korean Society of Mechanical Engineers, A
Volume	37
Issue number	3
DOIs	https://doi.org/10.3795/KSME-A.2013.37.3.387
Publication status	Published - 2013 Mar

Keywords

CRDM
FEA
PWSCC
RPV
Sensitivity Analysis

ASJC Scopus subject areas

Mechanical Engineering

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10.3795/KSME-A.2013.37.3.387

Cite this

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title = "Sensitivity analysis of nozzle geometry variables for estimating residual stress in rpv CRDM penetration nozzle",

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).",

keywords = "CRDM, FEA, PWSCC, RPV, Sensitivity Analysis",

author = "Bae, {Hong Yeol} and Oh, {Chang Young} and Kim, {Yun Jae} and Kim, {Kwon Hee} and Chae, {Soo Won} and Kim, {Ju Hee}",

year = "2013",

month = mar,

doi = "10.3795/KSME-A.2013.37.3.387",

language = "English",

volume = "37",

pages = "387--395",

journal = "Transactions of the Korean Society of Mechanical Engineers, A",

issn = "1226-4873",

publisher = "Korean Society of Mechanical Engineers",

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T1 - Sensitivity analysis of nozzle geometry variables for estimating residual stress in rpv CRDM penetration nozzle

AU - Bae, Hong Yeol

AU - Oh, Chang Young

AU - Kim, Yun Jae

AU - Kim, Kwon Hee

AU - Chae, Soo Won

AU - Kim, Ju Hee

PY - 2013/3

Y1 - 2013/3

N2 - 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).

AB - 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).

KW - CRDM

KW - FEA

KW - PWSCC

KW - RPV

KW - Sensitivity Analysis

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U2 - 10.3795/KSME-A.2013.37.3.387

DO - 10.3795/KSME-A.2013.37.3.387

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SN - 1226-4873

VL - 37

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JO - Transactions of the Korean Society of Mechanical Engineers, A

JF - Transactions of the Korean Society of Mechanical Engineers, A

IS - 3

ER -

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

Abstract

Keywords

ASJC Scopus subject areas

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