Assessment of Applicability of Bentonite Clay-Based Ceramics for Immobilization of Radioactive Waste from Pyrochemical Processing of Spent Nuclear Fuel

被引:0
|
作者
Poglyad, S. S. [1 ]
Dmitrieva, O. S. [1 ]
Bezdnyakova, E. A. [1 ]
Romanova, O. V. [1 ]
机构
[1] Res Inst Atom Reactors, Dimitrovgrad 433510, Ulyanovsk Oblas, Russia
关键词
waste from pyrochemical reprocessing of spent nuclear fuel; matrix for radioactive waste immobilization; matrix based on bentonite clay;
D O I
10.1134/S1066362223070135
中图分类号
O65 [分析化学];
学科分类号
070302 ; 081704 ;
摘要
The applicability of bentonite clay-based ceramics for immobilization of waste from pyrochemical reprocessing of spent nuclear fuel-spent electrolyte, which consists of alkali metal chlorides, was studied. Main matrix characteristics such as the phase composition, mechanical durability, leaching rate and microstructure were studied. The results obtained were compared to the requirements to the cement compound, formulated in NP-019-15 document. The matrix was considered to be suitable for the radioactive waste disposal.
引用
收藏
页码:S160 / S166
页数:7
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