Improvement of the Neutronic Performance of the PACER Fusion Concept Using Thorium Molten Salt with Reactor Grade Plutonium

被引：0
作者：
Adem Acır
机构：
[1] Gazi University,Department of Energy Systems Engineering, Faculty of Technology
来源：
Journal of Fusion Energy | 2013年 / 32卷
关键词：
Molten salt; Tritium breeding; PACER; Plutonium molten salt; Thorium;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
In this study, the improvement of neutronic performance of a dual purpose modified PACER concept has been investigated. Flibe as the main constituent are fixed as 92% coolant. ThF4 is mixed with increased mole-fractions of RG-PuF4 starting by 0 mol % up to 1 mol %. TBR variations for all the investigated salts with respect to the RG-PuF4 contents are computed. Tritium self-sufficiency is provided with the ThF4 when the adding RG-PuF4 content is higher than 0.75%. The energy multiplication of the blanket is increased as 70% with adding RG-PuF4 contents to ThF4. High quality fissile isotope 233U are produced with increasing RG-PuF4. DPA and helium production increases with increased RG-PuF4 content in molten salt. Radiation damage with dpa <1.7 and He <3.3 ppm after a plant operation period of 30 years will be well below the damage limit values.
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页码：11 / 14
页数：3
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