钚
核工程
沸腾
氧化铀
冷却液
混合氧化物燃料
铀
中子慢化剂
铍
钍燃料循环
环境科学
物理
核物理学
中子温度
中子
热力学
中子截面
工程类
作者
V. Yu. Zhdamirov,V. I. Naumov,Yu. N. Volkov
标识
DOI:10.1134/s1063778820100269
摘要
The article presents the concept of a channel-type reactor with a combined cooled moderator. The moderator consists of ceramic beryllium oxide and a liquid moderator—water with a possible variation in its composition due to the ratio between light water and heavy water components. Variants of fuel cycles based on the combination of “power” plutonium with depleted uranium, regenerated uranium, and thorium are analyzed. Quantitative estimates of the consumption of raw materials and the transformation of the isotopic composition of the irradiated fuel components are presented. The issues of safety and the possibility of controlling the reactivity coefficient by the density of the boiling coolant when changing the fuel cycle are discussed.
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