Published 1999 | Version v1
Journal article

Radiolysis studies for the long-term storage of 233U oxides

Description

The 233U that has been removed from the Molten Salt Reactor Experiment (MSRE) at the Oak Ridge National Laboratory (ORNL) as UF6 will be converted to uranium oxide and placed into long-term storage. After conversion, radiolysis of fluorides that remain in the uranium oxide matrix may produce gaseous products (e.g., F2, HF) that are deleterious to storage containers, either through pressurization or corrosion. Consequently, an experimental program has been conducted to evaluate these potential radiolytic effects

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
81
Journal Page Range
p. 88-89
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
American Nuclear Society 1999 Winter Meeting
Dates
14-18 Nov 1999
Place
Long Beach, CA (United States)