"Ion sputtering-thermal separation" technology for spent nuclear fuel processing

被引:2
|
作者
Petrovskaya, Anna S. [1 ,2 ]
Tsyganov, Alexander B. [1 ,2 ]
Surov, Sergey V. [3 ]
Kladkov, Andrey Yu. [3 ]
机构
[1] Intro Micro LLC, Ligovskiy Ave 29A,Off 12-N, St Petersburg 191036, Russia
[2] InnoPlasmaTech LLC, Line 17 VO, 4-6,Liter B,Off K-202, St Petersburg 191034, Russia
[3] Sci & Innovat JSC ROSATOM, Kadashevskaya Embankment 32-2,Bldg 1, Moscow 115035, Russia
关键词
Spent nuclear fuel; Closed nuclear fuel cycle; Ion sputtering-thermal separation technology; High-pressure microplasma discharge; Plasma application for nuclear power; Spent nuclear fuel separation into elemental; components; ISOTOPE-SEPARATION; PLASMA;
D O I
10.1016/j.nucengdes.2021.111561
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
The purpose of this work is to develop a new technology for spent nuclear fuel (SNF) processing, aimed at effective solution of the problem - creation of a closed nuclear fuel cycle. We offer "dry " technology "Ion sputtering -thermal separation " (IS-TS) for a spent nuclear fuel processing with its separation into elemental components by differentiation them due to individual variations in the saturated vapor temperature. Separation is provided through SNF tablets sputtering-evaporation at the high-pressure microplasma discharge (pressure about 1 atm.) in an inert gas (e.g., argon) flow with the following separation into elemental components along the diffusion tube sections maintained at the specified temperature levels. According to IS-TS technology, at the current density of 5 A/cm(2) and voltage of 600 V, mass processing rate of SNF is estimated 0,01 g/sec or -1 kg/ day. Accounting of additional effect of thermal tablet evaporation further increase processing rate value. In this way, a single block of 100 discharge-diffusion tubes, operating in parallel, is estimated to recover 30 ton of SNF per year. The microplasma high-pressure discharge in an inert gas environment used in IS-TS technology is also applied for decontamination of irradiated reactor graphite and internal surfaces of metal structures of the primary circuit of NPU.
引用
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页数:4
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