Intact and Degraded Criticality Calculations for the Codisposal of Shippingport PWR Fuel in a Waste Package

The purpose of this calculation is to characterize the criticality safety concerns for the codisposal of Shippingport pressurized water reactor (SP PWR) spent nuclear fuel (SNF) contained in a standardized Department of Energy (DOE) SNF canister, and high-level waste (HLW) glass in a waste package (WP) placed in a Monitored Geologic Repository (MGR). The result of this calculation will be used to evaluate criticality issues and provide input for the DOE SNF canister design, referred to as "the canister" in this document. The calculation method employs the use of MCNP Version 4B2 computer code (Ref. 1) to calculate the effective neutron multiplication factor (k-eff) for various geometrical configurations of SP PWR SNF.