Numerical Prediction of Maximum Load-Carrying Capacity of Cracked Alloy 690TT Steam Generator Tubes

Jun Young Jeon, Yun Jae Kim, Jin Weon Kim, Kuk Hee Lee, Jong Sung Kim

Research output: Contribution to journalArticle

4 Citations (Scopus)

Abstract

This paper presents a finite element (FE) simulation technique to predict maximum load-carrying capacity of cracked steam generator tubes and its application to Alloy 690TT tubes. The simulation method is based on a simplified version of the stress modified fracture strain model. The damage model is determined from tensile test and one cracked tube test data. Predicted maximum pressures are compared with 23 test data of axial through-wall and surface cracked Alloy 690TT steam generator tubes. Comparison with experimental data shows good agreement.

Original languageEnglish
Article number041601
JournalJournal of Pressure Vessel Technology, Transactions of the ASME
Volume138
Issue number4
DOIs
Publication statusPublished - 2016 Aug 1
Externally publishedYes

Fingerprint

Steam generators
Load limits

Keywords

  • alloy 690 steam generator tube
  • burst pressure prediction
  • finite element ductile fracture simulation
  • multiaxial fracture strain model

ASJC Scopus subject areas

  • Safety, Risk, Reliability and Quality
  • Mechanics of Materials
  • Mechanical Engineering

Cite this

Numerical Prediction of Maximum Load-Carrying Capacity of Cracked Alloy 690TT Steam Generator Tubes. / Jeon, Jun Young; Kim, Yun Jae; Kim, Jin Weon; Lee, Kuk Hee; Kim, Jong Sung.

In: Journal of Pressure Vessel Technology, Transactions of the ASME, Vol. 138, No. 4, 041601, 01.08.2016.

Research output: Contribution to journalArticle

@article{916ba1eebdd546fa8c0896b369e06157,
title = "Numerical Prediction of Maximum Load-Carrying Capacity of Cracked Alloy 690TT Steam Generator Tubes",
abstract = "This paper presents a finite element (FE) simulation technique to predict maximum load-carrying capacity of cracked steam generator tubes and its application to Alloy 690TT tubes. The simulation method is based on a simplified version of the stress modified fracture strain model. The damage model is determined from tensile test and one cracked tube test data. Predicted maximum pressures are compared with 23 test data of axial through-wall and surface cracked Alloy 690TT steam generator tubes. Comparison with experimental data shows good agreement.",
keywords = "alloy 690 steam generator tube, burst pressure prediction, finite element ductile fracture simulation, multiaxial fracture strain model",
author = "Jeon, {Jun Young} and Kim, {Yun Jae} and Kim, {Jin Weon} and Lee, {Kuk Hee} and Kim, {Jong Sung}",
year = "2016",
month = "8",
day = "1",
doi = "10.1115/1.4031746",
language = "English",
volume = "138",
journal = "Journal of Pressure Vessel Technology, Transactions of the ASME",
issn = "0094-9930",
publisher = "American Society of Mechanical Engineers(ASME)",
number = "4",

}

TY - JOUR

T1 - Numerical Prediction of Maximum Load-Carrying Capacity of Cracked Alloy 690TT Steam Generator Tubes

AU - Jeon, Jun Young

AU - Kim, Yun Jae

AU - Kim, Jin Weon

AU - Lee, Kuk Hee

AU - Kim, Jong Sung

PY - 2016/8/1

Y1 - 2016/8/1

N2 - This paper presents a finite element (FE) simulation technique to predict maximum load-carrying capacity of cracked steam generator tubes and its application to Alloy 690TT tubes. The simulation method is based on a simplified version of the stress modified fracture strain model. The damage model is determined from tensile test and one cracked tube test data. Predicted maximum pressures are compared with 23 test data of axial through-wall and surface cracked Alloy 690TT steam generator tubes. Comparison with experimental data shows good agreement.

AB - This paper presents a finite element (FE) simulation technique to predict maximum load-carrying capacity of cracked steam generator tubes and its application to Alloy 690TT tubes. The simulation method is based on a simplified version of the stress modified fracture strain model. The damage model is determined from tensile test and one cracked tube test data. Predicted maximum pressures are compared with 23 test data of axial through-wall and surface cracked Alloy 690TT steam generator tubes. Comparison with experimental data shows good agreement.

KW - alloy 690 steam generator tube

KW - burst pressure prediction

KW - finite element ductile fracture simulation

KW - multiaxial fracture strain model

UR - http://www.scopus.com/inward/record.url?scp=84974644136&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=84974644136&partnerID=8YFLogxK

U2 - 10.1115/1.4031746

DO - 10.1115/1.4031746

M3 - Article

VL - 138

JO - Journal of Pressure Vessel Technology, Transactions of the ASME

JF - Journal of Pressure Vessel Technology, Transactions of the ASME

SN - 0094-9930

IS - 4

M1 - 041601

ER -