Published July 1985 | Version v1
Journal article Metadata-only

Study on leak-before-break in PWR primary loop

Creators

  • 1. Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan). Energy and Environment Lab.

Description

Rationalization of design of nuclear piping system based on leak-before-break concept has been established for high-energy piping systems in West Germany and USA. In this report, it is intended to grasp the present status on change in design requirement and leak-before-break analysis methods. It is found that the design guides based on leak-before-break are under construction in USA and West Germany. As a ductile fracture criterion, both the net-section stress criterion and the J-integral method are widely used. Finally, leak-before-break assessment for PWR primary piping is made using the simplified method. (author)

Additional details

Publishing Information

Journal Title
Denryoku Chuo Kenkyusho Hokoku
Journal Issue
no.285006
Series
Denryoku Chuo Kenkyusho Hokoku.
CODEN
DCKHD

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
17065542
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CRACK PROPAGATION; CRACKS; FAILURES; FEDERAL REPUBLIC OF GERMANY; LEAKS; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; RESTRAINTS; REVIEWS; STRESSES; SYSTEM FAILURE ANALYSIS; TUBES; USA
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; DEVELOPED COUNTRIES; DOCUMENT TYPES; ENRICHED URANIUM REACTORS; EUROPE; NORTH AMERICA; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS