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Characteristics of Spent Fuel, High-Level Waste, and Other Radioactive Wastes Which May Require Long-Term Isolation, Rev. 0

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 REPORT TO THE PRESIDENT AND THE CONGRESS BY THE SECRETARY OF ENERGY ON THE NEED FOR A SECOND REPOSITORY

The Nuclear Waste Policy Act of 1982, as amended (NWPA), establishes a process for the siting, construction and operation of one or more national repositories for permanent disposal of the Nation’s spent nuclear fuel (SNF) and high-level radioactive waste (HLW). In 1987, after the Department of Energy (the Department or DOE) had conducted studies of nine potential repository sites located throughout the United States, Congress amended the NWPA and selected the Yucca Mountain site in Nye County, Nevada as the only site for further study for the first national repository.

NRC Waste Confidence Positions

In response to the remand of the U.S. Court of Appeals for the District of Columbia Circuit (Minnesota v. NRC, 602 F.2d 412 (1979)), and as a continuation of previous proceedings conducted in this area by NRC (44 Fed. Reg. 61,372), the Commission initiated a generic rulemaking proceeding on October 25, 1979.

YMP Preliminary Wet Handling Facility Throughput Study

This study describes the development of a preliminary throughput estimate for a Wet Handling Facility (WHF)/ used fuel repackaging factility. This study estimates the throughput for the WHF License Application design for a repository at Yucca Mountain as of September 2007. This design freeze allowed for the development of the throughput study without having to accommodate for minor updates to the facility design and documentation leading up to the License Application.

THE ROLE OF INDIAN TRIBES IN AMERICA’S NUCLEAR FUTURE

Indian tribes have voiced their tribal issues in the United States‘ nuclear effort since its
inception, with the siting of what would become Los Alamos National Laboratory adjacent to the
San Ildefonso Pueblo Reservation and the Hanford plutonium production works along waterways
shared with the Yakama Nation and other Indian tribes. The siting of a proposed repository at
Yucca Mountain, Nevada along with other activities conducted on the Nevada National Security
Site (NNSS) (formerly the Nevada Test Site), increased the need for the United States

ORIGEN-S Decay Data Library and Half-Life Uncertainties

The results of an extensive update of the decay data of the ORIGEN-S library are presented
in this report. The updated decay data were provided for both the ORIGEN-S and ORIGEN2
libraries in the same project. A complete edit of the decay data plus the available half-life
uncertainties are included in Appendix A. A detailed description of the types of data contained in the
library, the format of the library, and the data sources are also presented. Approximately 24% of the

Managing Commercial High-Level Radioactive Waste

After more than 20 years of commercial nuclear power, the Federal Government has yet to develop a broadly supported policy for fulfilling its legal responsibility for the final isolation of high-level radioactive waste. OTA's study concludes that until such a policy is adopted in law, there is a substantial risk that the false starts, shifts of policy, and fluctuating support that have plagued the final isolation program in the past will continue.

Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel

The purpose of this calculation report, Range of Applicability and Bias Determination for Postclosure
Criticality of Commercial Spent Nuclear Fuel, is to validate the computational method used to perform
postclosure criticality calculations. The validation process applies the criticality analysis methodology
approach documented in Section 3.5 of the Disposal Criticality Analysis Methodology Topical Report.1
The application systems for this validation consist of waste packages containing transport, aging, and

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