Isotopic Dilution of 233U with Depleted Uranium for Criticality Safety in Processing and Disposal
Conference
·
OSTI ID:505729
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
The disposal of excess 233U as waste is being considered. Because 233U is a fissile material, a key requirement for processing 233U to a final waste form and disposing of it is the avoidance of nuclear criticality. For many processing and disposal options, isotopic dilution is the most feasible and preferred option to avoid nuclear criticality. Isotopic dilution is dilution of fissile 233U with non-fissile 238U. The use of isotopic dilution removes any need to control nuclear criticality in process or disposal facilities through geometry or chemical composition. Isotopic dilution allows the use of existing waste management facilities that are not designed for significant quantities of fissile materials to be used for processing and disposing of 233U. The amount of isotopic dilution required to reduce criticality concerns to reasonable levels was determined in this study to be approximately 0.53 wt % 233U. The numerical calculations used to define this limit consisted of a homogeneous system of silicon dioxide (SiO2), water (H2O), 233U and depleted uranium (DU) in which the ratio of each component was varied to learn the conditions of maximum nuclear reactivity. About 188 parts of DU (0.2 wt % 23U) are required to dilute 1 part of 233U to this limit in a water-moderated system with no SiO2 present. Thus, for the U.S. inventory of 233U, several hundred metric tons of DU would be required for isotopic dilution.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-96OR22464
- OSTI ID:
- 505729
- Report Number(s):
- CONF-970926--9; ON: DE97006434
- Country of Publication:
- United States
- Language:
- English
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