Safety of pyroelectrochemical reprocessing of spent BOR-60 fuel

被引:0
|
作者
Serebryakov, VV
Kirillovich, AP
Bychkov, AV
Kormilitsyn, MV
Ishunin, VS
机构
[1] State Science Center of the Russian Federation, Scientific-Research Institute of Nuclear Reactors
关键词
8;
D O I
10.1007/s10512-005-0205-7
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 results of an investigation of the safety of reprocessing 15.5 kg of spent BOR-60 fuel are presented. The absolute amounts of radioactive aerosols entering the ventilation system of the pyroelectrochemical setup during the reprocessing of spent fuel are determined. The transfer of radionuclides from fuel into aerosols is estimated. This makes it possible to obtain an expression for the expected inflow of radioactive substances from the setup, depending on the amount of materials handled in the technological scheme. The data presented on the possibility of obtaining large amounts of uranium and plutonium in the finished product when their content in the solid wastes is negligible are presented. Estimates are made of the irradiation of workers at all stages of the process.
引用
收藏
页码:270 / 277
页数:8
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