Published 1993
| Version v1
Book
Methodology of predicting materials failures in advanced nuclear systems
Description
Experiences in the nuclear power plant operation and the fixing of unexpected component failures, originated mainly from corrosion damages, have led to a base methodology of predicting, correcting and preventing failures. Some analogies of the algorithm developed have been extended to the evolution of reliable materials, their testing and database construction in the development of advanced systems for next generation. An illustrative topic was chosen from the materials development and reliability testing carried out in the development of an advanced HTGR for process heat applications. Possibility and issues in making the similar approach in the case of nuclear fusion is also discussed
Additional details
Publishing Information
- Publisher
- NACE International.
- Imprint Place
- Houston, TX (United States)
- ISBN
- 1-877914-65-7
- Imprint Title
- 12th International corrosion congress: Proceedings
- Imprint Pagination
- 571 p.
- Journal Page Range
- p. Plenary.20-Plenary.42.
Conference
- Title
- 12. international corrosion congress.
- Dates
- 19-24 Sep 1993.
- Place
- Houston, TX (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25058619
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORROSION; DATA; FAILURE MODE ANALYSIS; FAILURES; HEAT RESISTANT MATERIALS; HTGR TYPE REACTORS; LMFBR TYPE REACTORS; MATERIALS TESTING; NUCLEAR FACILITIES; PHYSICAL RADIATION EFFECTS; PROCESS HEAT REACTORS; REACTOR MATERIALS; RESEARCH PROGRAMS; THERMONUCLEAR REACTOR MATERIALS; WATER COOLED REACTORS
- Descriptors DEC
- BREEDER REACTORS; CHEMICAL REACTIONS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; INFORMATION; LIQUID METAL COOLED REACTORS; MATERIALS; POWER REACTORS; RADIATION EFFECTS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TESTING
Optional Information
- Secondary number(s)
- CONF-9309150--.