BN-800快堆中的钚配置:钚同位素和增殖的评估

IF 0.7 Q3 INTERNATIONAL RELATIONS Science & Global Security Pub Date : 2014-09-02 DOI:10.1080/08929882.2014.952578
M. Kütt, F. Frieß, M. Englert
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引用次数: 8

摘要

根据2000年签署并于2010年修订的《钚管理和处置协议》,俄罗斯和美国同意各自处理34吨多余的武器钚。俄罗斯计划将钚用作其BN-600和BN-800钠冷快堆的燃料。本文分析了BN-800型核心堆模型中乏燃料中钚同位素载体的增殖层和不增殖层,增殖层中的钚产量,燃料中不同钚浓度的增殖层比,以及可能的年材料吞吐量。研究发现,堆芯中任何乏燃料的钚-239含量都低于90%,但使用增殖毯,反应堆可以被配置为钚的净生产者,即使增殖比低于1,而且在毯中生产的钚将是武器级的。
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Plutonium Disposition in the BN-800 Fast Reactor: An Assessment of Plutonium Isotopics and Breeding
According to the Plutonium Management and Disposition Agreement, which was signed in 2000 and amended in 2010, Russia and the United States agree to dispose of 34 tons of excess weapon plutonium each. Russia plans to use the plutonium as fuel in its sodium-cooled fast reactors BN-600 and BN-800. This article analyzes BN-800 core models with and without breeding blankets for the plutonium isotopic vector in spent fuel, plutonium production in breeding blankets, breeding ratios for different plutonium concentrations in fuel, and possible annual material throughput. It finds that any spent fuel in the core contains less than 90 wt% plutonium-239, but using breeding blankets the reactor can be configured to be a net producer of plutonium, even with a breeding ratio below one, and that plutonium produced in blankets will be weapon-grade.
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来源期刊
Science & Global Security
Science & Global Security INTERNATIONAL RELATIONS-
CiteScore
1.00
自引率
14.30%
发文量
8
期刊最新文献
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