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
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Fuel irradiation of the first batches produced for the Chinese HTR-10
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
نویسندگان
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