This workshop will introduce participants to the use, accuracy, and limitations of methodologies/tools employed for the evaluation of safety and safeguards for spent nuclear fuel pools. In the area of pool criticality safety, the industry state-of-the-art conservative methodology and the recently developed VT3G best-estimate methodology are discussed. In the area of pool safeguards, participants will become acquainted with the methodology and capability of the VT3G developed INSPCT-S tool for detection of fuel diversion in a spent fuel pool. Hands-on sessions with example problems will occupy the main portion of the workshop. Participants will receive lecture notes, input files, and utility software for processing of inputs and outputs.
Where: Virginia Tech Research Center, 900 Glebe Road, Arlington, Virginia 22203
Industry state-of-the-art conservative methodology
VT3G best estimate methodology
MCNP eigenvalue and subcritical multiplication calculations
Tools for generating input files
Uncertainties and limitations of different methodologies