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Dose Rate Calculations for the 2-MCO/2-DHLW Waste Package

Dose Rate Calculations for the 2-MCO/2-DHLW Waste Package

Author(s)
OCRWM
Publication Date
The objective of this calculation is to determine the dose rates on the external surfaces of the waste package (WP) containing two Hanford defense high-level waste (DHLW) glass canisters and two Hanford multi-canister overpacks (MCO). Each MCO is loaded with the N Reactor spent nuclear fuel (SNF). The information provided by the sketches attached to this calculation is that of the potential design for the WP type considered in this calculation.
high level waste radiation protection storage hanford site 2-mco/2-dhlw dose calculation multi-canister overpack defense

N-Reactor Spent Nuclear Fuel Criticality Calculations

N-Reactor Spent Nuclear Fuel Criticality Calculations

Author(s)
CRWMS
Publication Date

The purpose of this calculation is to characterize the criticality safety aspects of N-Reactor fuel stored in a Department of Energy spent nuclear fuel (DOE-SNF) canister that contains four Multi-Canister Overpacks (MCO's). These calculations will be done to support the analysis that will be done to demonstrate concept viability related to pre-emplacement storage and use in the Monitored Geologic Repository (MGR) environment for the pre-closure time frame.

criticality monitored geologic repository storage preclosure n reactor doe snf wp multi-canister overpack bba000000-01717-0210-00005

Summary of National and International Radioactive Waste Management Programs 1979

SED Publication Type

Summary of National and International Radioactive Waste Management Programs 1979

Author
K. M. Harmon
Publication Date

Many nations and international agencies are working to develop improved technology and industrial capability for nuclear fuel cycle and waste management operations. The effort in some countries is limited to research in university laboratories on treating low-level waste from reactor plant operations.

doe waste management siting fuel cycle pnl-2941
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