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The CFD Simulation on Grid-Spacer and Wire for Lead-Cooled Fast Reactor

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Proceedings of The 20th Pacific Basin Nuclear Conference (PBNC 2016)

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Abstract

In order to separate the fuel rods along radial in one fuel assembly, there are two ways, one is using the grid-spacer, the other is using the wire-wrapped. In this paper, choose three situation (with grid-spacer, with wire-wrapped, without any of them) to show the effects of grid-spacer or wire-wrapped on average temperature, average pressure, coolant velocity, rod temperature. On the other hand, two planes (cross section at the mid-plane through the spacer and cross section 2 cm downstream of the spacer) were carried to analyze effect on temperature and velocity. The results show that the grid-spacer or wire-wrapped has little effect on the average temperature in the sub-channel. But it is clearly shown that the effect on the maximum temperature, average pressure, and coolant velocity. Moreover, local heat transfer was enhanced at the grid-spacer and wire.

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Correspondence to Gao Xinxin .

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Xinxin, G., Ruoxiang, Q. (2017). The CFD Simulation on Grid-Spacer and Wire for Lead-Cooled Fast Reactor. In: Jiang, H. (eds) Proceedings of The 20th Pacific Basin Nuclear Conference. PBNC 2016. Springer, Singapore. https://doi.org/10.1007/978-981-10-2314-9_25

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  • DOI: https://doi.org/10.1007/978-981-10-2314-9_25

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  • Publisher Name: Springer, Singapore

  • Print ISBN: 978-981-10-2313-2

  • Online ISBN: 978-981-10-2314-9

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