Open AccessRadiation Characteristics of Borosilicate Glass Containing High-Level Waste
Author(s) -
A. S. Aloy,
A. I. Blokhin,
P. A. Blokhin,
Н. В. Ковалев
Publication year - 2020
Publication title -
radioaktivnye othody
Language(s) - English
Resource type - Journals
ISSN - 2587-9707
DOI - 10.25283/2587-9707-2020-3-93-100
Subject(s) - borosilicate glass , high level waste , radioactive waste , spent nuclear fuel , radium , nuclear engineering , radiation , materials science , radionuclide , radiochemistry , waste management , environmental science , metallurgy , engineering , chemistry , nuclear physics , physics
The article presents computational and analytical studies dealing with radiation characteristics of liquid high-level waste vitrified using borosilicate glass (BSS). To confirm the quality of glass on a time scale of up to 10 4 years and more, computational and experimental studies are performed to identify the dose loads on the BSS from all types of radiation. The paper presents the results of computational studies focused on radionuclide composition and radiation characteristics of a BSS produced during the reprocessing of spent nuclear fuel from VVER-1000 reactors based on a method developed by JSC Radium Institute named after V. G. Khlopin.