Engineering Analysis And Design
|
Engineering Analysis And Design
|
|
|
Multi-Canister Overpack (MCO) & Transportation Cask SARPQ-Metrics provided the thermal
safety analysis of the MCO and MCO transportation cask for the safety analysis
report for packaging (SARP). The SARP evaluated operations at the DOE Hanford
Site and covered the transfer of spent nuclear fuel (SNF) between the K-Basins
and the Cold Vacuum Drying Facility (CVDF) The calculations involved working with SNF Project personnel to establish the appropriate reaction rate equations for chemical heat and gas generation, the bounding reaction areas for the damaged fuel and scrap elements, and the operational constraints to be applied to the analysis. The generation of hydrogen gas from the reaction of the uranium metal with water was an important part of the analysis. Two distinct modes of transfer were evaluated: water flooded during the transfer between the K-Basins and the CVDF, and in a dry, inert atmosphere during the transfer between the CVDF and the CSB. In an associated work scope with the MCO Transportation Cask SARP, Q-Metrics authored the thermal chapter for the MCO Topical Report. This work involved coordinating the work of a number of contractors, providing a consistency check between the various parts of the work, and assembling the V&V documentation for the work. Q-Metrics
was also called upon to address comments
received on the SARP analysis
from the Dept. Of Energy's review team and
from the DNFSB (Defense Nuclear
Fuel Safety Board) and to provide peer review
support for miscellaneous studies conducted by other
engineering organizations. |
|
|
