Qi Zhang , Yi Zhou , Junsen Fu , Hanyang Gu , Tenglong Cong
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引用次数: 0
Abstract
In the presented work, the single-phase heat transfer behaviors of the 4 × 4 helical cruciform fuel (HCF) assembly is investigated by numerical simulation. The non-uniform wall temperature of the HCF element and the evolution of mean wall temperature along the rod length are analyzed. Besides, the effects of helical pitch and ratio of blade diameter and elbow diameter on the heat transfer are paid particular concern. According to the results, the wall temperature continues to increase along the path between the elbow and the blade lee side, and the peak wall temperature is always observed at the end of blade lee side. While the blades of the neighboring HCF elements getting closer, the mean wall temperature is increased by 1.2 °C–4.4 °C rapidly. The hot spots are generated with the rotation angle of n × 90°. By increasing the rotation angle, the heat transfer coefficient (HTC) of the HCF assembly continues to fluctuate with the maximum amplitude of ±10 %, and the rotation angle for the fluctuation period is 90°. With shorter helical pitch, the mean wall temperature is reduced while more hot spots are generated. In addition, the distribution of mean wall temperature along the rod length is almost not changed by the cross-section shape.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.