Published July 1999 | Version v1
Journal article

Development of modified piping evaluation diagram for leak-before-break application to Korean next generation reactor

  • 1. Sungkyunkwan Univ., Suwon (Korea, Republic of). Sch. of Mech. Eng.
  • 2. Department of Mechanical Engineering, Induk Institute of Technology, Seoul (Korea, Republic of)
  • 3. Korea Electric Power Research Institute, Daejon (Korea, Republic of)

Description

Recently, the piping evaluation diagram (PED) is accepted in nuclear industry for an efficient application of leak-before-break (LBB) concept to piping system at an initial piping design stage. The objective of this paper is to develop the modified PED, which can account for the variation of the material properties of the PED development stage and those of the assembly stage. For this purpose, a parametric study was performed to investigate the effect of stress-strain curve on the detectable leakage crack length and the effect of fracture resistance curve on the LBB allowable load. Finite element analyses were also performed to investigate the effect of stress-strain curve on the LBB allowable load. Finally, a modified PED was proposed as a function of crack length and the allowable safe shutdown earthquake load. The LBB analyses based on the modified PED are in good agreement with those based on the traditional PED. By adopting the modified PED, the variation of material properties can be considered in the LBB analysis and the computing times required for the application of LBB during the design process can be considerably reduced. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
191
Journal Issue
2
Journal Page Range
p. 135-145
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
2. International workshop on the integrity of nuclear components
Dates
20-21 Apr 1998
Place
Tokyo (Japan)

INIS

Country of Publication
Netherlands
Country of Input or Organization
Switzerland
INIS RN
31002795
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CRACKS; FAILURES; FINITE ELEMENT METHOD; FRACTURE MECHANICS; REACTOR MATERIALS; STEELS
Descriptors DEC
ALLOYS; CALCULATION METHODS; CARBON ADDITIONS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICS; NUMERICAL SOLUTION; TRANSITION ELEMENT ALLOYS

Optional Information

Notes
15 refs.