Application of probabilistic fracture mechanics to pressure vessels and piping of nuclear power plants. JSME activity
Creators
- 1. Toyohashi Univ. of Technology, Toyohashi, Aichi (Japan)
- 2. Tokyo Univ., Tokyo (Japan)
- 3. Tokyo Electric Power Co., Inc., Tokyo (Japan)
- 4. Toshiba Corp., Tokyo (Japan)
- 5. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
- 6. Central Research Inst. of Electric Power Industry, Tokyo (Japan)
Description
Probabilistic fracture mechanics (PFM) is a key technique in probabilistic safety assessment (PSA) of nuclear power plants. The Japan Society of Mechanical Engineers (JSME) has a research committee on PFM applications to pressure vessels and piping of nuclear power plants (RC111[5]). This paper reviews the activity of the committee. The activity consists of surveys of available data, benchmark calculations and sensitivity calculations. The surveys are on analysis methods, modeling of defects and data on defects, loading and material properties. Surveyed methods and data are used in the succeeding calculations. They are performed on three problems, piping, pressure vessel subject to normal loading and pressure vessel subject to pressurized thermal shock (PTS) loading. The last one is especially important in the safety analysis and will be summarized by another paper of this conference. This paper summarizes the sensitivity calculations of pressure vessels and piping subject to normal loading. Parameters reviewed here are: crack depth distribution, neutron irradiation, uncertainty of fracture toughness, ISI interval, and loading conditions. (author)
Additional details
Publishing Information
- Imprint Title
- ICONE-3: Proceedings of the 3rd JSME/ASME joint international conference on nuclear engineering. Volume 1
- Imprint Pagination
- 701 p.
- Journal Page Range
- p. 411-416
Conference
- Title
- 3. JSME/ASME joint international conference on nuclear engineering
- Acronym
- ICONE-3
- Dates
- 23-27 Apr 1995
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 38007321
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CRACKS; FRACTURE MECHANICS; FRACTURE PROPERTIES; JAPANESE ORGANIZATIONS; NEUTRON FLUENCE; NUCLEAR POWER PLANTS; PIPES; PROBABILISTIC ESTIMATION; REACTOR VESSELS; RESEARCH PROGRAMS; SENSITIVITY ANALYSIS; SIZE
- Descriptors DEC
- CALCULATION METHODS; CONTAINERS; MECHANICAL PROPERTIES; MECHANICS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS; TUBES
Optional Information
- Notes
- 8 refs., 9 figs., 3 tabs.