HTGR Knowledge Base
Conference Article: Status of the research and development at JAERI on the C/C composite control rod for HTGR
Eto, M.; Ishiyama, S.; Ugachi, H. (Japan Atomic Energy Research Inst., Ibaraki (Japan))Abstract
Control rod elements made of carbon-carbon composites were prepared and fracture-tested, aiming at the development of the more heat-resistant control rod which may impose the less restriction on the operation and shutdown of the HTGR. The control rod elements included pellet holder, lace truck and pin of PAN- or pitch-based composite material. On the basis of the results of fracture tests on the unirradiated elements, those made of PAN-based material were selected for an irradiation experiment. The irradiation was carried out in JRR-3 at 900 +- 50 deg. C to a maximum neutron fluence of 1 x 1025 n/m2 (E>29fJ). Fracture tests of the elements indicated that both fracture load and fracture displacement enough to assure the integrity of a control rod were maintained even after the irradiation. It was also found that both fracture strength and strain increased when applied load was parallel to the fiber felt plane, whereas the strength increase and strain decrease were observed for the load applied against the plane.
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key words: Gas Cooled Reactor, Nuclear Technology
- Reference:
- Specialists meeting on graphite moderator lifecycle behaviour. Bath (United Kingdom). 24-27 Sep 1995.
- International Atomic Energy Agency, Vienna (Austria)
- IAEA-TECDOC--901, pp:205-214
- International Atomic Energy Agency, Vienna (Austria)
