The management of spent nuclear fuel (SNF) and defense high level waste (HLW) is a complex sociotechnical
systems challenge. Coordinated, reliable, and safe performance will be required over very long
periods of time within evolving social and technical contexts. To accomplish these goals, a waste
management system will involve a host of facilities for interim storage and longterm disposal, a
transportation infrastructure, and research and development centers. The complexity of SNF and HLW

The objectie of this calculation is to document the Grand Gulf, Unit 1, (GG1) fuel depletion calculations. The GG1 reactor is a boiling water reactor (BWR) owned and operated by Entergy Operations Inc. The Commercial Reactor Criticality (CRC) evaluations support the development and validation of the neutronic models used for criticality analyses involving commercial spent nuclear fuel in a geologic repository. This calculation is performed as part of the evaluation CRC program. This report is an engineering calculation supporting the burnup credit methodology of YMP 2000 (Ref.

The objective of this safety requirements publication is to set down the protection objectives and criteria for geological disposal and to establish the requirements that must be met to ensure the safety of this disposal option, consistent with the established principles of safety for radioactive waste management.

The purpose of this calculation is to estimate the probability of misloading a commercial spent
nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or
burnup) outside the waste package design. The waste package designs are based on the expected
commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1
and Table 1). For this calculation, a misloaded waste package is defined as a waste package that

This letter is written by Former Wyoming Governor Mike Sullivan to inform the Fremont County Commissioners of his conclusion to decline the MRC facility.

About 20,000 metric tons of spent, or used, nuclear
fuel have accumulated since the beginning of commercial
nuclear power prbduction in the United States. At the end
of the currently licensed period of all existing nuclear power
plants and those under construction, the amount of spent
nuclear fuel is expected to total 87,000 metric tons.
Thus far, practically all of the spent nuclear fuel is
stored in water-filled pools at reactor sites. However, space
does not exist in the pools to store all the spent fuel expected

In February, 2011 the Blue Ribbon Commission (BRC) on America’s Nuclear Future requested the Department of Energy
(DOE) to provide a white paper summarizing the quantities and characteristics of potential waste generated by various
nuclear fuel cycles. The BRC request expressed interest in two classes of radioactive wastes:
 Existing waste that are or might be destined for a civilian deep geologic repository or equivalent.
 Potential future waste, generated by alternative nuclear fuel cycles (e.g. wastes from reprocessing, mixed-oxide

The effective termination of the Yucca Mountain program by the U.S. Administration in 2009
has further delayed the construction and operation of a permanent disposal facility for used fuel
and high level radioactive waste (HLW) in the United States. In concert with this decision, the
President directed the Energy Secretary to establish the Blue Ribbon Commission on America’s
Nuclear Future to review and provide recommendations on options for managing used fuel and

This report evaluates the relative economics of alternative fuel cycles compared to the current
U.S. once-through fuel cycle, including concepts under consideration by the U.S. Department of
Energy’s (DOE) Global Nuclear Energy Partnership (GNEP). EPRI utilized a model developed
by the Nuclear Energy Agency (NEA), Steady-state analysis Model for Advanced Fuel Cycle
Schemes (SMAFS), to evaluate fuel cycle alternatives. The report also evaluates potential
financing options for a fuel recycling facility. Please note that this report contains preliminary

This report evaluates the radiological impacts during postulated accidents associated with the
transportation of spent nuclear fuel to the proposed Yucca Mountain repository, using the
RADTRAN 5.5 computer code developed by Sandia National Laboratories. RADTRAN 5.5 can
be applied to estimate the risks associated both with incident-free transportation of radioactive
materials as well as with accidents that may be assumed to occur during transportation. Incidentfree
transportation risks for transport of spent nuclear fuel to Yucca Mountain were evaluated in

This report presents the results of a dynamic simulation analysis for deployment of advanced light water reactors (LWRs) and fast burner reactors, as proposed by the Global Nuclear Energy Partnership (GNEP) program. Conditions for the analysis were selected for their potential to challenge the nuclear fuel simulation codes that were used, due to the large variations in nuclear fuel composition for the burner reactors before equilibrium conditions are approached. The analysis was performed in a U.S.

The main question before the Transportation and Storage Subcommittee was whether the United States should change its approach to storing and transporting spent nuclear fuel (SNF) and high-level radioactive waste (HLW) while one or more disposal facilities are established.