Behavior of complex loaded components in the creep range
Creators
- 1. Staatliche Materialpruefungsanstalt, Stuttgart (Germany)
Description
Components of power and other plants which operate in the elevated temperature range, where time-dependent creep deformation occurs are exposed to complex loading. Creep and fatigue loading but also corrosive influences constitute essential factors limiting the lifetime of these components. Typical loading situations are explained using examples of power plant components. In this paper selected research projects running in the Federal Republic of Germany and in particular at MPA Stuttgart and the results obtained to date are presented. The projects concentrate on the treatment of creep-fatigue on nozzles of piping and valve casings, the damage process in pipe bends under static creep loading, the life assessment of a dissimilar weldment in the watersteam circuit of the HTR plant and the failure and deformation behavior of a reactor tank wall of an LMFBR under creep loading with superimposed bending moment
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0810-6
- Imprint Title
- Fatigue, fracture, and risk 1991
- Imprint Pagination
- 210 p.
- Journal Page Range
- p. 141-146.
Conference
- Title
- 1991 American Society of Mechanical Engineers (ASME) pressure vessels and piping conference.
- Dates
- 23-27 Jun 1991.
- Place
- San Diego, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23053348
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CREEP; DEFORMATION; DESIGN; DYNAMIC LOADS; ENVIRONMENTAL EFFECTS; HTR REACTOR; LMFBR TYPE REACTORS; MATERIALS TESTING; NOZZLES; PERFORMANCE TESTING; PIPE JOINTS; REACTOR COMPONENTS; RESEARCH PROGRAMS; SAFETY ANALYSIS; STRESS ANALYSIS; THERMAL FATIGUE; TIME DEPENDENCE
- Descriptors DEC
- BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FATIGUE; FBR TYPE REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; JOINTS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; POOL TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TESTING; THERMAL REACTORS; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-910602--.