Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fueled with low-enriched uranium
نویسندگان
چکیده
Abstract To provide a reliable and comprehensive data reference for core geometry design of graphite-moderated low-enriched uranium fueled molten salt reactors, the influences geometric parameters on temperature coefficient reactivity (TCR) at an assembly level were characterized. A four-factor formula was introduced to explain how different coefficients behave in terms fuel volume fraction size. The results show that (FSTC) is always negative owing more density over-moderated region or Doppler under-moderated region. Depending channel spacing, graphite moderator (MTC) can be positive. Furthermore, with smaller spacing likely exhibit MTC. As increases, FSTC first weakens then effect gradually weakening from positive feedback decreasing. Meanwhile, MTC as thermal utilization caused by deteriorates. Thus, TCR strengthens, mainly because change coefficient. size magnitude decreases monotonously weakened coefficient, whereas changes enhanced feedback. Then, weakens. Therefore, achieve proper TCR, particularly MTC, strongly recommended.
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ژورنال
عنوان ژورنال: Nuclear Science and Techniques
سال: 2023
ISSN: ['1001-8042', '2210-3147']
DOI: https://doi.org/10.1007/s41365-023-01216-0