Study of thorium–uranium based molten salt blanket in a fusion–fission hybrid reactor
Study of thorium–uranium based molten salt blanket in a fusion–fission hybrid reactor
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DOI：
10.1016/j.fusengdes.2012.03.020
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发表时间：
2012-08
影响因子：
1.7
通讯作者：
J. Zhao;Yongwei Yang;Zhiwei Zhou
中科院分区：
文献类型：
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作者：
J. Zhao;Yongwei Yang;Zhiwei Zhou
聚变-裂变共生反应堆覆盖层不仅可以使用固体燃料，还可以使用液体燃料。 F-Li-Be熔盐反应堆的运行记录非常成功，因此选择F-Li-Be包层进行研究。熔盐具有多种适合聚变裂变应用的特性。燃料材料铀和钍溶解在F-Li-Be熔盐中。组合程序 COUPLE 用于熔盐层的中子学分析。对几种情况进行了计算和比较。不仅研究了不同燃料的影响，还研究了熔盐的厚度以及熔盐中6Li的浓度。初步研究表明，在F-Li-Be熔盐层中添加钍铀钚燃料，组分为71%LiF-2%BeF2-13.5%ThF4-8.5%UF4-5%PuF3，熔盐厚度为40cm，自然浓度为6Li时，可以获得合适的层能量倍增系数和TBR。结果表明，钍铀熔盐可用于聚变裂变共生反应堆的包层。熔盐层的研究对于聚变-裂变共生反应堆的设计具有一定的价值。
Not only solid fuels, but also liquid fuels can be used for the fusion–fission symbiotic reactor blanket. The operational record of the molten salt reactor with F–Li–Be was very successful, so the F–Li–Be blanket was chosen for research. The molten salt has several features which are suited for the fusion–fission applications. The fuel material uranium and thorium were dissolved in the F–Li–Be molten salt. A combined program, COUPLE, was used for neutronics analysis of the molten salt blanket. Several cases have been calculated and compared. Not only the influence of the different fuels have been studied, but also the thickness of the molten salt, and the concentration of the6Li in the molten salt. Preliminary studies indicate that when thorium–uranium–plutonium fuels were added into a F–Li–Be molten salt blanket and with a component of 71% LiF–2% BeF2–13.5% ThF4–8.5% UF4–5% PuF3, and also with the molten salt thickness of 40cm and natural concentration of6Li, the appropriate blanket energy multiplication factor and TBR can be obtained. The result shows that thorium–uranium molten salt can be used in the blanket of a fusion–fission symbiotic reactor. The research on the molten salt blanket must be valuable for the design of fusion–fission symbiotic reactor.