The objective of this calculation is to characterize the nuclear criticality safety concerns
associated with the codisposal of the Department of Energy’s (DOE) Enrico Fermi (EF) Spent
Nuclear Fuel (SNF) in a 5-Defense High-Level Waste (5-DHLW) Waste Package (WP) and
placed in a Monitored Geologic Repository (MGR). The scope of this calculation is limited to
the determination of the effective neutron multiplication factor (keff) for the degraded mode
internal configurations of the codisposal WP. The results of this calculation and those of Ref. 8

The Nuclear Waste Policy Act of 1982, as amended, established a statutory basis
for managing the nation’s civilian (or commercially produced) spent nuclear
fuel. The law established a process for siting, developing, licensing, and constructing
an underground repository for the permanent disposal of that waste.
Utilities were given the primary responsibility for storing spent fuel until it is
accepted by the Department of Energy (DOE) for disposal at a repository —
originally expected to begin operating in 1998. Since then, however, the repository

Dear Mr. Frazier:
At our request, the Commission staff is in the process of assembling information on the costs and financing of the US program to manage used fuel and high-level nuclear wastes. To assist in the completion of this effort, it would be most helpful if the Department could provide the information listed int the attachment.
...

GAO Storage Study Request

The purpose of this calculation is to perform nuclear criticality calculations for High-Level Waste (HLW) glass to support the criticality safety analysis of normal operations and off-normal conditions associated with the receipt, handling and loading of HLW glass canisters into 5-DHLW/DOE SNF Waste Packages (WPs) and 2-MCO/2-DHLW WPs in the surface facilities, in addition to the emplacement of loaded and sealed WPs in the sub-surface facility.

Thirty spent fuel samples obtained from boiling-water-reactor (BWR) fuel pins have been
modeled at Oak Ridge National Laboratory using the SAS2H sequence of the SCALE code system.
The SAS2H sequence uses transport methods combined with the depletion and decay capabilities
of the ORIGEN-S code to estimate the isotopic composition of fuel as a function of its burnup
history. Results of these calculations are compared with chemical assay measurements of spent fuel
inventories for each sample. Results show reasonable agreement between measured and predicted

The Analysis of the Total System Life Cycle Cost (TSLCC) of the Civilian Radioactive Waste Management Program represents the Office of Civilian Radioactive Waste Management's most recent estimate of the costs to dispose of the Nations's spent nuclear fuel (SNF) and high-level radioactive waste (HLW). This TSLCC analysis projects all Program costs through 2119 for a surrogate, single potential repository. The design and emplacement concepts in this TSLCC analysis are the same as those presented in the Monitored Geologic Repository Project Description Document.

Spent Fuel Project Office Interim Staff Guidance - 8

This study examines concerns raised by the U.S. Department of Energy (DOE) in its planning for transition from active waste site management and remediation to what the department terms “long-term stewardship.” It examines the scientific, technical, and organizational capabilities and limitations that must be taken into account in planning for the long-term institutional management of the department’s numerous waste sites that are the legacy to this country’s nuclear weapons program. It also identifies characteristics and design criteria for effective longterm institutional management.

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013