Published April 2019 | Version v1
Journal article Metadata-only

Numerical validation of burst pressure estimation equations for steam generator tubes with multiple axial surface cracks

Creators

  • 1. Dept. of Mechanical Engineering, Korea University, Seoul (Korea, Republic of)
  • 2. Dept. of Nuclear Engineering, Chosun University, Gwangju (Korea, Republic of)

Description

This paper provides further validation of the burst pressure estimation equations for multiple axial surface cracked steam generator tubes, recently proposed by the authors based on analytical local collapse load approach against systematic FE damage analysis results of Alloy 690 tubes with twin axial surface cracks. Wide ranges of the relative crack depth and multiple crack configurations are considered. Comparison shows good agreements, giving sufficient confidence of the proposed equations

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Technology
Journal Volume
51
Journal Issue
2
Series
22 refs, 10 figs, 3 tabs
Journal Page Range
p. 579-587
ISSN
1738-5733

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
50064669
Subject category
S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
CRACKS; DAMAGE; EQUATIONS; INCONEL 690; STEAM GENERATORS; SURFACES; TUBES; VALIDATION
Descriptors DEC
ALLOY-NI59CR30FE9; ALLOYS; BOILERS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; MATERIALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; TESTING; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS