Abstract
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.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
