A Program Research and Development Announcement (PRDA) was
initiated by DOE to solicit from industry new and novel ideas for
improvements in the nuclear waste management system. GA Technologies
Inc. was contracted to study a system utilizing a universal canister
which could be loaded at the reactor and used throughout the waste
management system.

This report describes a task performed in the Energy Material Transport,
Now Through 2000, System Characteristics and Potential Problems (Transportation
Problems) Project. This project was sponsored by the Department of Energy,
Environmental Control Technology Division. The DOE Project Monitor was
R. F. Garrison; Project Manager at PNL was J. G. DeSteese. A continuation of
the cask turnaround study is currently supported by the Transportation Technology
Center at Sandia National Laboratories, the DOE1s lead laboratory for Transportation

This three-volume report serves several purposes. The first volume provides an
introduction to the engineered materials effort for the Yucca Mountain Site
Characterization Project. It defines terms and outlines the history of selection and
characterization of these materials. A summary of the recent engineered barrier
system materials characterization workshop is presented, and the current candidate
materials are listed.

This report was prepared for the Secretary of Energy by a team of federal and contractor
personnel led by the Department’s Office of Nuclear Energy. The report assesses the technical
options for the permanent disposal of high-level radioactive waste (HLW) and spent nuclear fuel
(SNF) managed by the Department of Energy. Specifically, it considers whether DOE-managed HLW and
SNF should be disposed of with commercial SNF and HLW in one geologic repository or whether there

DOE/RW-0584

This three-volume report serves several purposes. The first volume provides an introduction to the engineered materials effort for the Yucca Mountain Site Characterization Project. It defines terms and outlines the history of selection and
characterization of these materials. A summary of the recent engineered barrier system materials characterization workshop is presented, and the current candidate materials are listed. The second volume tabulates design data for engineered

Spent Nuclear Fuel Management: Outreach Needed to Help Gain Public Acceptance for Federal Activities That Address Liability
GAO-15-141: Published: Oct 9, 2014. Publicly Released: Nov 12, 2014.

The Cyclic Integrated Reversible-Bending Fatigue Tester (CIRFT) can be used for
investigating the vibration integrity of spent nuclear fuel during transportation.This report is the R&D 100 submission related to the CIRFT.

This is the final report for the Argonne National Laboratory-East (ANL-E) Building 200
M-Wing Hot Cells Decontamination Project. The purpose of the project was to practically eliminate
the radioactive emissions of Rn-220 to the environment and to restore the hot cells to an empty
restricted use-condition. About 96.2 TBq (2,600 curies) per year of Rn-220 was being emitted at the
start of the project from the radioactive contaminants left in the hot cells at the end of the ANL-E
Proof-of-Breeding program work in 1985.

This is the final report for the Argonne National Laboratory-East (ANL-E) Building 200
M-Wing Hot Cells Decontamination Project. The purpose of the project was to practically eliminate
the radioactive emissions of Rn-220 to the environment and to restore the hot cells to an empty
restricted use-condition. About 96.2 TBq (2,600 curies) per year of Rn-220 was being emitted at the
start of the project from the radioactive contaminants left in the hot cells at the end of the ANL-E
Proof-of-Breeding program work in 1985.