کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
299577 | 511879 | 2006 | 7 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Fuel irradiation of the first batches produced for the Chinese HTR-10
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موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
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چکیده انگلیسی
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.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 236, Issue 1, January 2006, Pages 107–113
Journal: Nuclear Engineering and Design - Volume 236, Issue 1, January 2006, Pages 107–113
نویسندگان
Chunhe Tang, Xiaoming Fu, Junguo Zhu, Tongxiang Liang, Konstantin N. Koshcheyev, Alexandre V. Kozlov, Oleg G. Karlov, Yu.G. Degaltsev, Vladimir I. Vasiliev,