Published February 1990
| Version v1
Report
Results of the Japanese carbon steel pipe fracture program
Description
The paper summarizes a four-year program conducted for MITI on LBB applicability to carbon steel pipes. They conducted 28 straight pipe fracture experiments, and several elbow and tee cyclic loading to leakage tests. For the STS 42 carbon steel pipe investigated, it was concluded that the pipes reached limit load, hence elastic-plastic fracture analysis methods were not needed. As a final result of the program, it was concluded that the concept of LBB is applicable to carbon steel piping in LWRS. 7 figs., 5 tabs
Additional details
Publishing Information
- Imprint Title
- Leak-Before-Break: Further developments in regulatory policies and supporting research
- Imprint Pagination
- 350 p.
- Journal Page Range
- p. 13-32.
- Report number
- NUREG/CP--0109
Conference
- Title
- further developments in regulatory policies and supporting research.
- Acronym
- Seminar on leak-before-break
- Dates
- 11-12 May 1989.
- Place
- Taipei, Taiwan (China).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21054007
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CARBON STEELS; FRACTURE MECHANICS; GOVERNMENT POLICIES; INTERNATIONAL ORGANIZATIONS; JAPAN; LOSS OF COOLANT; MATERIALS TESTING; NUCLEAR POWER PLANTS; PIPES; REACTOR COOLING SYSTEMS; REGULATIONS; RESEARCH PROGRAMS
- Descriptors DEC
- ACCIDENTS; ALLOYS; ASIA; CARBON ADDITIONS; COOLING SYSTEMS; DEVELOPED COUNTRIES; IRON ALLOYS; IRON BASE ALLOYS; LAW; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; STEELS; TESTING; THERMAL POWER PLANTS
Optional Information
- Secondary number(s)
- CONF-8905290--.