Effect of stress holding on fatigue strength of nuclear graphite
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
Since graphite components in the HTTR (=High Temperature Engineering Test Reactor) are subjected to cyclic stress during reactor start-up, operation or shut-down, the design of the reactor requires the knowledge of cumulative fatigue damage of graphite materials. However, the number of reports on the cumulative fatigue damage of graphites are very limited. In this paper, the results of fatigue test in the mixed fatigue mode of cyclic and static stresses were reported on HTTR components graphite, IG -110, regarding the effects of stress hold time and static fatigue-cyclic fatigue interaction on cumulative fatigue damage of the graphite. The following results were derived: (1) Static fatigue failure of IG-110 graphite was observed at the stress level of more than 0.95 times as large as the mean tensile strength. (2) Fatigue life under cyclic stress was longer than that of mixed fatigue mode of cyclic and static stresses at the stress level of more than 0.85 times as large as the mean tensile strength. (3) Fatigue life of mixed fatigue mode decreased with increasing stress hold time. (4) Damage factor of static stress in the mixed fatigue mode was very small, and cumulative fatigue damage in this was smaller than 1. (author)
Additional details
Publishing Information
- Journal Title
- Zairyo
- Journal Volume
- 40
- Journal Issue
- 457
- Series
- Zairyo.
- Journal Page Range
- 1336-1340
- ISSN
- 0514-5163
- CODEN
- ZARYA
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 23027526
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DESTRUCTIVE TESTING; FATIGUE; GRAPHITE; HTTR REACTOR; MODERATORS; PHYSICAL RADIATION EFFECTS; REACTOR MATERIALS; TEMPERATURE RANGE 1000-4000 K; TENSILE PROPERTIES; TEST REACTORS; THERMAL STRESSES
- Descriptors DEC
- CARBON; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; NONMETALS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; STRESSES; TEMPERATURE RANGE; TEST FACILITIES; TESTING