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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

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report for Uruguay

SED Publication Type

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, National Report for Uruguay

Author
Uruguay
Publication Date

There are no nuclear power stations and no nuclear fuel cycle activities in Uruguay. There are only disused radioactive sources from medical and industrial practices and there is a disused conditioned neutron Pu-239 source with 185 TBq, waiting for its reshipment to the United States. This material is stored in the building in which it was an old research reactor. The application of the Convention is limited to radioactive waste arising from the medical, industrial and research applications of radioisotopes.

siting national report joint convention spent fuel management uruguay radioactive waste management
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