The fatigue strength of graphite and carbon materials for HTTR core components
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
Room temperature fatigue tests were carried out on graphite and carbon materials, which are used for the components in the core region of the HTTR, in the applied stress condition that R (=σ min / σ max)=-3, -1, 0 (PGX graphite), =-1, 0 (ASR-ORB carbon) and =-1 (IG-11 graphite). The data were analyzed by Price's method, homologous stress method and P-T-S diagram method to investigate which is the most appropriate to derive design S-N curves. Fatigue tests were also carried out at 980degC in vacuo on IG-11 graphite to clarify the effect of temperature on its fatigue strength. The results indicated: (1) Price's method was the most appropriate to analyze the data for a design S-N curve. (2) Fatigue strength decreased with decreasing R-value, with the less pronounced tendency for ASR-ORB. (3) Design S-N curves were obtained on PGX and ASR-ORB on the basis of the data analyzed by Price's method. (4) Fatigue strength of IG-11 at 980degC appeared to be almost the same as that for the room temperature fatigue strength, if the applied stress was normalized to the mean tensile strength at room temperature in vacuo. (author)
Availability note (English)
Available from INIS in electronic formFiles
29054906.pdf
Files
(1.2 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:ed00980a6bae2a005b1d1c3ef50d6e23
|
1.2 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 64 p.
- Report number
- JAERI-Research--98-024
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 29054906
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CARBON; COMPRESSION STRENGTH; FATIGUE; GRAPHITE; HTTR REACTOR; REACTOR CORES; STRESSES; TEMPERATURE RANGE 1000-4000 K; TENSILE PROPERTIES
- Descriptors DEC
- CARBON; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MECHANICAL PROPERTIES; NONMETALS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TEMPERATURE RANGE