Through-wall welding residual stress profiles for dissimilar metal nozzle butt welds in pressurized water reactors

Tae Kwang Song, Ji Soo Kim, Chang Young Oh, Yun-Jae Kim, Chi Yong Park, Kyoung Soo Lee

Research output: Contribution to journalArticle

8 Citations (Scopus)

Abstract

This paper provides approximate expressions for through-wall welding residual stresses in dissimilar metal nozzle butt welds of pressurized water reactors. An idealized shape of nozzle is proposed, based on which systematic elastic-plastic thermo-mechanical finite element analyses are conducted by varying the thickness and radius of the nozzle and the length of the safe-end. Based on the results, a through-wall welding residual stress profile for dissimilar metal nozzle butt welds is proposed by modifying the existing welding residual stress profile for austenitic pipe butt welds in the R6 procedure.

Original languageEnglish
Pages (from-to)624-641
Number of pages18
JournalFatigue and Fracture of Engineering Materials and Structures
Volume34
Issue number8
DOIs
Publication statusPublished - 2011 Aug 1

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Dissimilar metals
Pressurized water reactors
Residual stresses
Nozzles
Welding
Welds
Pipe
Plastics

Keywords

  • dissimilar metal nozzle butt welds
  • finite element analysis
  • pressurised water reactors
  • through-wall welding residual stress profile

ASJC Scopus subject areas

  • Mechanical Engineering
  • Mechanics of Materials
  • Materials Science(all)

Cite this

Through-wall welding residual stress profiles for dissimilar metal nozzle butt welds in pressurized water reactors. / Song, Tae Kwang; Kim, Ji Soo; Oh, Chang Young; Kim, Yun-Jae; Park, Chi Yong; Lee, Kyoung Soo.

In: Fatigue and Fracture of Engineering Materials and Structures, Vol. 34, No. 8, 01.08.2011, p. 624-641.

Research output: Contribution to journalArticle

Song, Tae Kwang ; Kim, Ji Soo ; Oh, Chang Young ; Kim, Yun-Jae ; Park, Chi Yong ; Lee, Kyoung Soo. / Through-wall welding residual stress profiles for dissimilar metal nozzle butt welds in pressurized water reactors. In: Fatigue and Fracture of Engineering Materials and Structures. 2011 ; Vol. 34, No. 8. pp. 624-641.
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