Experimental Check of the Suitability of an Iron Phosphate Ceramic for Immobilization of Radioactive Waste from Pyrochemical Reprocessing of Spent Nuclear Fuel
摘要
Abstract
The suitability of a matrix based on an iron phosphate ceramic (IPC) for immobilization of waste from pyrochemical reprocessing of spent nuclear fuel (spent electrolyte, a readily water-soluble fusion cake of alkali metal chlorides) was examined. The phase composition, chemical durability, and mechanical strength of the matrix material were studied. The matrix meets the requirements to a cement compound formulated in NP-019-15 regulation document and is suitable for radioactive waste disposal.