Assessment of current structural design methodology for high-temperature reactors based on failure tests
A mature design methodology, consisting of inelastic analysis methods, provided in Department of Energy guidelines, and failure criteria, contained in ASME Code Case N-47, exists in the United States for high-temperature reactor components. The objective of this paper is to assess the adequacy of this overall methodology by comparing predicted inelastic deformations and lifetimes with observed results from structural failure tests and from an actual service failure. Comparisons are presented for three types of structural situations: (1) nozzle-to-spherical shell specimens, where stresses at structural discontinuities lead to cracking, (2) welded structures, where metallurgical discontinuities play a key role in failures, and (3) thermal shock loadings of cylinders and pipes, where thermal discontinuities can lead to failure. The comparison between predicted and measured inelastic responses are generally reasonalbly good; quantities are sometimes overpredicted somewhat, and, sometimes underpredicted. However, even seemingly small discrepancies can have a significant effect on structural life, and lifetimes are not always as closely predicted. For a few cases, the lifetimes are substantially overpredicted, which raises questions regarding the adequacy of existing design margins.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6496824
- Report Number(s):
- CONF-8508114-1; ON: DE85016300
- Resource Relation:
- Conference: 5. international seminar on inelastic analysis and life prediction in high-temperature environment, Paris, France, 26 Aug 1985
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluated Iridium, Yttrium, and Thulium Cross Sections and Integral Validation Against Critical Assembly and Bethe Sphere Measurements
Predictability of long-term creep and rupture in a nozzle-to-sphere vessel model
Related Subjects
LMFBR TYPE REACTORS
DESIGN
REACTOR COMPONENTS
FAILURES
PIPES
REACTOR MATERIALS
STAINLESS STEELS
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MATERIALS
REACTORS
STEELS
210500* - Power Reactors
Breeding