By D A Reed; Oak Ridge National Laboratory. .; United States. Dept. of Energy.; United States. Dept. of Energy. Office of Scientific and Technical Information
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Extra info for Nuclear Criticality Safety of the DOT 9975 Container for237NpO2Storage, Handling, and Transport
4a and MCNP 4c2 were initially installed on ossws5 in April 2002. Quarterly reverifications have been routinely performed since then, with no detected problems. The most recent quarterly re-verifications were performed on March 28 and July 4, 2003. 4a NCS Model The NCS geometry model for all cases of this appendix consisted of a cuboid of edge dimension 100 cm. Mirror boundary conditions were imposed on all six faces of the cuboid to simulate a geometrically infinite system. For an infinite system, k∞ is independent of the mixture material density.
The volume fraction of the array occupied by the 237NpO2 payloads is small. Neutrons migrating through the Celotex find it less probable that a fissionable material volume is encountered; this results in greater neutron track length (and moderation) within the Celotex. These factors support consideration that the 237Np payloads and the hydrogen moderator of the Celotex are effectively "mixed" to an appreciable extent. The current SARP model for the DOT 9975 container underestimates the Celotex content as ~ 97 liters; the actual Celotex volume per container is ~ 116 liters.
Such a reconfiguration of a large number of HEU items, if possible, would require some severe, unlikely off-normal facility event. For this lesser-size HEU array, the array keff value was found to be independent of whether the DOT 9975 containers were loaded or not. 75-inches). This model considers that a hypothetical HEU accident might involve a small number of units. Again, the criticality condition of the fiducial HEU accumulation was found to be independent of whether 237NpO2 was present in the adjacent DOT 9975 container array.