Steady-state thermal-hydraulic analysis of SCWR assembly |
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Authors: | Xiaojing Liu and Xu Cheng |
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Affiliation: | (1) School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai, 200240, China |
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Abstract: | Among the six gen-IV reactor concepts recommended by the gen-IV international forum (GIF), supercritical water-cooled reactor
(SCWR), the only reactor with water as coolant, achieves a high thermal efficiency and, subsequently, has economic advantages
over the existing reactors due to its high outlet temperature. A thermal-hydraulic analysis of the SCWR assembly is performed
in this paper using the modified COBRA-IV code. Two approaches to reduce the hot channel factor are investigated: decreasing
the moderator mass flow and increasing the thermal resistance between moderator channel and its adjacent sub-channels. It
is shown that heat transfer deterioration cannot be avoided in SCWR fuel assembly. It is, therefore, highly required to calculate
the cladding temperature accurately and to preserve the fuel rod cladding integrity under heat transfer deterioration conditions.
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Translated from Nuclear Power Engineering, 2007, 28(5): 18–21, 58 译自: 核动力工程] |
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Keywords: | supercritical water-cooled reactor (SCWR) sub-channel analysis fuel assembly design heat transfer deterioration |
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