Neutronics calculations for denatured molten salt reactors: Assessing resource requirements and proliferation-risk attributes

被引:16
作者
Ahmad, Ali [1 ]
McClamrock, Edward B.
Glaser, Alexander
机构
[1] Princeton Univ, Program Sci & Global Secur, Princeton, NJ 08544 USA
关键词
Molten salt reactors; Denatured fuel; Proliferation resistance; FUEL;
D O I
10.1016/j.anucene.2014.08.014
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
Molten salt reactors (MSRs) are often advocated as a radical but worthwhile alternative to traditional reactor concepts based on solid fuels. This article builds upon the existing research into MSRs to model and simulate the operation of thorium-fueled single-fluid and two-fluid reactors. The analysis is based on neutronics calculations and focuses on denatured MSR systems. Resource utilization and basic proliferation-risk attributes are compared to those of standard light-water reactors. Depending on specific design choices, even fully denatured reactors could reduce uranium and enrichment requirements by a factor of 3-4. Overall, denatured single-fluid designs appear as the most promising candidate technology minimizing both design complexity and overall proliferation risks despite being somewhat less attractive from the perspective of resource utilization. (C) 2014 Elsevier Ltd. All rights reserved.
引用
收藏
页码:261 / 267
页数:7
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