UO2-liquid metal suspension fuel concept for enhanced passive safety of LWRs: A heat pipe case study

被引:1
作者
Greenquist, Ian [1 ]
机构
[1] Oak Ridge Natl Lab, Nucl Energy & Fuel Cycle Div, Oak Ridge, TN 37830 USA
关键词
Nuclear fuel; UO2; OpenMC; MOOSE; LIQUID-METAL; THERMAL-CONDUCTIVITY; ZIRCALOY-4; DENSITY; GAP; UO2;
D O I
10.1016/j.nucengdes.2022.111972
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This work proposes a novel fuel concept for use in light-water type reactors (LWRs): UO2 particles suspended in a low-melting-point liquid metal (LM). This new fuel form offers lower energy density and higher thermal con-ductivity, thus enhancing the fuel's thermal performance compared to sintered UO2 pellets. Two candidate alloys for the LM are proposed based on previous studies into accident-tolerant fuels: Bi-Pb-Sn and Pb-Sn. Ten research questions are provided to guide future development of this fuel.A simple heat pipe model was constructed by coupling a reactor physics code to a heat transport code and other physics modules. Scoping calculations were performed on this model core as a preliminary investigation into five of the research questions. A fuel with 13 wt% UO2 was shown to maintain a steady-state peak coolant channel wall temperature below 400 degrees C, and maintain criticality via self-regulating reactivity feedback.Shortcomings of the present model are discussed herein, along with proposed future model improvements and fuel development. The appendix provides an example of a reactor concept that could be developed to utilize this fuel, but more modeling and experimental work are needed before a full reactor concept can be developed.
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页数:11
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