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Conference Article: The Behavior of HTR-10 Fuel Under Irradiation

Tang Chunhe, Fu Xiaoming, Zhu Junguo, Institute of Nuclear Energy Technology, Beijing, CHINA; Konstantin N. Koshceev, Alexandre V. Kozlov, Institute of Nuclear Materials, Zarechny, RUSSIA; Oleg G. Karlov; Yu.G. Degaltsev, Vladimir I. Vasiliev, Russian Research Center “Kurchatov Institute” Moscow, RUSSIA

Abstract

The irradiation test of 4 spherical fuel elements sampled randomly from the first and second product batches, which were produced for the 10 MW High Temperature Gas-cooled Test Reactor (HTR-10), ended up in January 2003 in Russian IVV-2M reactor. The maximum burnup and fast neutron fluence of the irradiated 4 fuel elements reached 107000MWd/tU and 1.31×1021n/cm2, respectively. All the fission gas release rate curves kept small fluctuation under average fuel temperature, ~1000C. The post-irradiation examination was finished before July 2004. In-pile heating test of SFE7 in capsule 5 led to the failure of about 6% coated particles at temperature that was much higher 1600C.

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key words: HTR-10; Spherical fuel element; Irradiation test; Post-irradiation examination
Reference:
Proceedings of the Conference on High Temperature Reactors, Beijing, China, September, 22-24, 2004
International Atomic Energy Agency, Vienna (Austria)
HTR-2004, pp:1-17