Conceptual Design of a Micro Nuclear Reactor for Canadian Arctic Communities

被引:2
|
作者
Crowell, Jordan [1 ]
Nichita, Eleodor [1 ]
机构
[1] Ontario Tech Univ, Fac Energy Syst & Nucl Sci, Oshawa, ON, Canada
基金
加拿大自然科学与工程研究理事会;
关键词
Micro nuclear reactor; lead cooled; graphite moderated;
D O I
10.1080/00295450.2022.2135334
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
Small Canadian arctic communities rely on diesel generators for their electricity needs. Providing such generators with fuel year round presents logistical challenges because of inclement weather and the long transportation distances involved. This work presents the conceptual design of a 10-MW(thermal) microreactor that can be used to provide 3.5 MW of electricity as well as district heating to arctic communities. The reactor has a lead-cooled and graphite-moderated core with 13 vertical fuel channels containing high-assay low-enriched uranium fuel enriched to 10%. The core is enclosed in a unpressurized reactor vessel and is passively cooled through natural convection. Stirling engines are used to drive the electrical generators. The hot cylinders of the Stirling engines are located in the unpressurized reactor vessel and are heated directly by the primary coolant. Preliminary neutronic and thermal-hydraulic analyses of the core indicate that the design is technically feasible and that the reactor can function for 2 years and 9 months without refueling.
引用
收藏
页码:504 / 514
页数:11
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