Open AccessCalculation of 1.25% 235U enriched UO2 solution safe slab, safe cylinder diameter, minimum safe mass, and ion exchange module for the CVDF
Author(s) -
S.P. Roblyer
Publication year - 1997
Language(s) - English
Resource type - Reports
DOI - 10.2172/325429
Subject(s) - fissile material , limiting , slab , nuclear engineering , uranium , radioactive waste , homogeneous , material balance , materials science , environmental science , chemistry , nuclear physics , process engineering , physics , engineering , structural engineering , mechanical engineering , metallurgy , thermodynamics , neutron
Support calculations were performed to establish safe parameters such as fissionable material slab thickness, diameter and safe mass. These calculations were performed by MCNP for the balance of plant equipment that contains homogeneous UO{sub 2} solutions with a maximum enrichment of 1.25 Wt% {sup 235}U . The calculations were performed with the most limiting concentration of moderator and reflection so that only the safety parameters identified in the problem description need to be controlled. These calculations represent the most limiting cases for all uranium enrichments and transuranic levels due to fuel exposure for balance of plant equipment used for handling of waste water containing fissionable materials from the MCO draining and drying activities