The purpose of this report, and the information contained in the associated computerized data bases, is to establish the DOE/OCRWM reference characteristics of the radioactive waste materials that may be accepted by DOE for emplacement in the mined geologic disposal system as developed under the Nuclear Waste Policy Act of 1982. This report provides relevant technical data for use by DOE and its supporting contractors and is not intended to be a policy document.

The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for all spent fuels and high-level wastes (HLW) that will eventually be disposed of in a geologic repository. The purpose of this document, and the information contained in the associated computerized data bases and supporting technical reports, is to provide the technical characteristics of the radioactive waste materials that will (or may) be accepted by DOE for interim storage in an MRS or emplacement in a repository as developed under the Nuclear Waste Policy Act Amendment of 1987.

This report has been prepared by an ad-hoc Working Group (WG) formed by ANDRA (France), NUMO (Japan), NAGRA (Switzerland) and ENRESA (Spain) in May 2003, after the EDRAM meeting held in Valencia to study the situation in the different EDRAM member countries regarding the treatment of radioactive waste ownership and management of long-term liabilities.

The Department of Energy (DOE), pursuant to the Atomic Energy Act of 1954
as amended, the Energy Reorganization Act of 1974, the Department of Energy
Organization Act of 1977, and the Nuclear Waste Policy Act of 1982 (the Act),
has the responsibility to provide for the disposal of high-level radioactive
waste and spent nuclear fuel.* The DOE selected mined geologic repositories
as the preferred means for the disposal of commercially generated high-level
radioactive waste and spent fuel (Federal Register, Vol. 46, p. 26677, May 14,

This report presents results from a parametric study of equilibrium fuel cycle costs for a closed fuel cycle with multi-recycling of plutonium in fast reactors (FRs) compared to an open, once-through fuel cycle using PWRs. The study examines the impact on fuel cycle costs from changes in the unit costs of uranium, advanced PUREX reprocessing of discharged uranium dioxide (UO2) fuel and fast-reactor mixed-oxide (FR-MOX) fuel, and FR-MOX fuel fabrication.

Expanding interest in nuclear power and advanced fuel cycles indicate that use of mixed-oxide (MOX) fuel in the current and new U.S. reactor fleet could become an option for utilities in the coming decades. In light of this renewed interest, EPRI has reviewed the substantial knowledge base on MOX fuel irradiation in light water reactors (LWRs). The goal was to evaluate the technical feasibility of MOX fuel use in the U.S. reactor fleet for both existing and advanced LWR designs (Generation III/III+).

Within the context of long-term waste management and sustainable nuclear fuel supply, there continue to be discussions regarding whether the United States should consider recycling of light-water reactor (LWR) spent nuclear fuel (SNF) for the current fleet of U.S. LWRs. This report presents a parametric study of equilibrium fuel cycle costs for an open fuel cycle without plutonium recycling (once-through) and with plutonium recycling (single-recycling using mixed-oxide, or MOX, fuel), assuming an all-pressurized water reactor (PWR) fleet.

In 2007 the OECD Nuclear Energy Agency (NEA) Radioactive Waste Management Committee
(RWMC) launched a four-year project on the topics of reversibility and retrievability in geological
disposal. The goal of the project studies and activities (www.oecd-nea.org/rwm/rr) was to
acknowledge the range of approaches to reversibility and retrievability (R&R), rather than to
recommend a specific approach, and to provide a basis for reflection rather than to lead towards

The purpose of this document is to provide the requirements rationale for the current version of the Preliminary Transportation, Aging and Disposal Canister System Performance Specification; WMO-TADCS-000001.

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

Ever since the 1950s, plutonium, used in fas reactors, has been seen as the key to unlocking the vast energy resource contained in the the world's uranium reserves. However, the reductions in expected nuclear reactor installation rates, combined with discovery of additional uranium, have led to a lengthening in the perceived time interval before fast reactors, the most effective users of plutonium, will make large demands on plutonium supplies. THere are several options concerning its use or storage in the meantime.

This report presents the analyses and results for the potential occurrence of external criticality events which could result from plutonium waste forms emplaced in a geologic repository similar to the one being developed at Yucca Mountain. The analyses evaluate both the MOX spent fuel and the immobilized plutonium waste forms in a repository if the waste package has degraded and if the fissile material has migrated to the invert and out into the far-field.

The OECD Nuclear Energy Agency (NEA) Forum on Stakeholder Confidence (FSC) acts as a centre for informed exchange of knowledge and experience regarding stakeholder interaction and public participation in radioactive waste management. It promotes an open discussion among members and stakeholders, across institutional boundaries, and between technical and non-technical actors, in an atmosphere of trust and mutual respect. As such, the FSC is, first and foremost, a learning organisation.

As part of the plutonium waste form development and down-select process, repository analyses have been conducted to evaluate the long-term performance of these forms for repository acceptance. Intact and degraded mode criticality analysis of mixed oxide (MOX) spent fuel is presented in Volume I, while Volume II presents the evaluations of the waste form containing plutonium immobilized in a ceramic matrix.

The IAEA has published guidance on particular elements of radioactive waste and spent fuel management,
such as establishing nuclear technical and regulatory infrastructure, relevant financing schemes, national policy
and strategies, multinational approaches and other aspects linked to building nuclear power plants. The present
publication is intended to provide a concise summary of key issues related to the development of a sound radioactive
waste and spent nuclear fuel management system. It is designed to brief countries with small or newly established

In the course of producing electrical power in light water reactors (LWRs), the uranium
fuel accumulates fission products until the fission process is no longer efficient.for power
production. At that point the fuel is removed from the reactor and stored in water basins
to allow radioactivity to partially decay before further disposition. This fuel is referred
to as "spent fuel." Although spent fuel as it is discharged from a reactor is intensely
radioactive, it has been stored safely in moderate quantities for decades. Spent fuel could