Published October 2012 | Version v1
Miscellaneous

Estimation of stress intensity factors for circumferential cracked pipes under welding residual stress filed

  • 1. Korea Univ., Seoul (Korea, Republic of)
  • 2. Power Engineering Research Institute, Seoul (Korea, Republic of)
  • 3. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

Description

Recently, stress corrosion cracking(SCC) have been found in dissimilar metal welds of nozzles in some pressurized water reactors and on low carbon stainless steel piping systems of boiling water reactors. The important factor of SCC is the residual stress field caused by weld. For the evaluation of crack growth analysis due to SCC, stress intensity factor under a residual stress field should be estimated. Several solutions for stress intensity factor under residual stress field were recommended in flaw assessment codes such as the American Society of Mechanical Engineers (ASME) Section XI, R6, American Petroleum Institute (API579). Some relevant works have been studied. Dong et al. evaluated stress intensity factors in welded structures. Miyazaki et al. estimated stress intensity factors of surface crack in simple stress fields. This paper presents a simple method to estimate stress intensity factors in welding residual stress field. For general application, results of structure integrity assessment codes KI solutions were compared Finite element analyses of welding simulation and cracked pipes are described. Comparison results of KI solutions and proposed simplified solution are presented in the works

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2012 autumn meeting of the KNS
Dates
24-26 Oct 2012
Place
Kyoungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
44062963
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
A CODES; CARBON STEELS; CRACKS; PIPES; PWR TYPE REACTORS; RESIDUAL STRESSES; STRESS CORROSION; STRESS INTENSITY FACTORS; WELDING
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; COMPUTER CODES; CORROSION; ENRICHED URANIUM REACTORS; FABRICATION; IRON ALLOYS; IRON BASE ALLOYS; JOINING; POWER REACTORS; REACTORS; STEELS; STRESSES; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
12 refs, 2 figs