Exploring the Use of Alumina Nanofluid as Emergency Coolant for Nuclear Fuel Bundle

被引:10
作者
Chinchole, A. S. [1 ]
Dasgupta, Arnab [1 ]
Kulkarni, P. P. [1 ]
Chandraker, D. K. [1 ]
Nayak, A. K. [1 ]
机构
[1] Bhabha Atom Res Ctr, Reactor Engn Div, Mumbai 400085, Maharashtra, India
关键词
nanofluids; rod bundle; quenching; CONVECTIVE HEAT-TRANSFER; FRICTION FACTOR; WATER; PERFORMANCE; FLOW; TUBE;
D O I
10.1115/1.4041441
中图分类号
O414.1 [热力学];
学科分类号
摘要
Nanofluids are suspensions of nanosized particles in any base fluid that show significant enhancement of their heat transfer properties at modest nanoparticle concentrations. Due to enhanced thermal properties at low nanoparticle concentration, it is a potential candidate for utilization in nuclear heat transfer applications. In the last decade, there have been few studies which indicate possible advantages of using nanofluids as a coolant in nuclear reactors during normal as well as accidental conditions. In continuation with these studies, the utilization of nanofluids as a viable candidate for emergency core cooling in nuclear reactors is explored in this paper by carrying out experiments in a scaled facility. The experiments carried out mainly focus on quenching behavior of a simulated nuclear fuel rod bundle by using 1% Alumina nanofluid as a coolant in emergency core cooling system (ECCS). In addition, its performance is compared with water. In the experiments, nuclear decay heat (from 1.5% to 2.6% reactor full power) is simulated through electrical heating. The present experiments show that, from heat transfer point of view, alumina nanofluids have a definite advantage over water as coolant for ECCS. Additionally, to assess the suitability of using nanofluids in reactors, their stability was investigated in radiation field. Our tests showed good stability even after very high dose of radiation, indicating the feasibility of their possible use in nuclear reactor heat transfer systems.
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页数:7
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