Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
299577 | Nuclear Engineering and Design | 2006 | 7 Pages |
Abstract
An irradiation test of four spherical fuel elements (SFE) had been performed in the Russian reactor IVV-2M. The elements were sampled randomly from the first and second product batches which were manufactured for the 10 MW high-temperature gas-cooled test reactor (HTR-10). The maximum burnup of the irradiated fuel elements reached 107,000 MWd/tU and the maximum fast neutron fluence was 1.31 × 1025 m−2. The release-to-birth rate ratio (R/B) did not increase significantly during irradiation. However, an in-pile heating-up test of element SFE 7 in Capsule 5 led to a failure of approximately 6% of the coated particles. After the test it was estimated that the fuel temperature had very likely been much higher than the intended 1600 °C.
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Authors
Chunhe Tang, Xiaoming Fu, Junguo Zhu, Tongxiang Liang, Konstantin N. Koshcheyev, Alexandre V. Kozlov, Oleg G. Karlov, Yu.G. Degaltsev, Vladimir I. Vasiliev,