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Radioactive waste management in the former USSR

Description: Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems … more
Date: June 1, 1992
Creator: Bradley, D.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status report on LWR spent fuel IAEA leach tests

Description: Spent light-water-reactor (LWR) fuel with an average burnup of 28,000 MWd/MTU was leach-tested at 25/sup 0/C using a modified version of the International Atomic Energy Agency procedure. Leach rates were determined from tests conducted in five different solutions: deionized water, sodium chloride (NaCl), sodium bicarbonate (NaHCO/sub 3/), calcium chloride (CaCl/sub 2/) and Waste Isolation Pilot Plant B brine solutions. Elemental leach rates are reported based on the release of /sup 90/Sr + /sup… more
Date: March 1, 1980
Creator: Katayama, Y.B.; Bradley, D.J. & Harvey, C.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Leaching of actinides and technetium from simulated high-level waste glass

Description: Leach tests were conducted using a modified version of the IAEA procedure to study the behavior of glass waste-solution interactions. Release rates were determined for Tc, U, Np, Pu, Am, Cm, and Si in the following solutions: WIPP B salt brine, NaCl (287 g/l), NaCl (1.76 g/1), CaCl/sub 2/ (1.66 g/l), NaHCO/sub 3/ (2.52 g/l), and deionized water. The leach rates for all elements decreased an order of magnitude from their initial values during the first 20 to 30 days leaching time. The sodium bic… more
Date: August 1, 1979
Creator: Bradley, D.J.; Harvey, C.O. & Turcotte, R.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Waste Isolation Safety Assessment Program. Technical progress report for FY-1978

Description: Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE) is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectat… more
Date: July 1, 1979
Creator: Brandstetter, A.; Harwell, M.A.; Howes, B.W.; Benson, G.L.; Bradley, D.J.; Raymond, J.R. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Proceedings of the Task 2 workshop Waste Isolation Safety Assessment Program

Description: The reports from the workshop on waste form release rate analysis are presented. The workshop started with overview presentations on the Office of Nuclear Waste Isolation (ONWI), the Waste Isolation Safety Assessment Program (WISAP), WISAP Task 2 (Waste Form Release Rate Analysis), and WISAP Task 4 (Sorption/Desorption Analysis). Technical presentations followed in these areas: leaching studies on spent fuels, leaching studies on high-level waste glass, waste form surface science experiments, r… more
Date: January 1, 1979
Creator: Bradley, D.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radioactive contamination of the Arctic Region, Baltic Sea, and the Sea of Japan from activities in the former Soviet Union

Description: Contamination of the Arctic regions of northern Europe and Russia, as well as the Sea of Japan, may become a potential major hazard to the ecosystem of these large areas. Widespread poor radioactive waste management practices from nuclear fuel cycle activities in the former Soviet Union have resulted in direct discharges to this area as well as multiple sources that may continue to release additional radioactivity. Information on the discharges of radioactive materials has become more commonpla… more
Date: September 1, 1992
Creator: Bradley, D.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Leaching of fully radioactive high-level waste glass

Description: As part of continuing Department of Energy (DOE)-sponsored studies in waste management, the Pacific Northwest Laboratory (PNL) has been conducting the High-Level Waste Immobilization Program. The purpose of this program is to develop and demonstrate technology for incorporating nuclear wastes into final waste forms. The preparation and leach testing of fully radioactive, zinc borosilicate glass, which was prepared from power reactor waste, are described. Leach testing using the International At… more
Date: September 1, 1978
Creator: Bradley, D.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

History of prototype high level waste Canister SS-9 while in air and water storage

Description: Canister SS-9 was filled with high-level phosphate ceramic waste material in March 1969. Following 1.2 years water storage at 50/sup 0/C, 3.5 years hot air storage at 400 to 500/sup 0/C, and 10 months water storage at 50/sup 0/C, the canister failed. The canister has three visible cracks, one of which is 13 in. long. It was concluded from metallography that failure was due to stress-assisted intergranular attack enhanced by metal sensitization during the hot air storage period, and a high chlor… more
Date: November 1, 1977
Creator: Bradley, D.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Annual report on the Characterization on the high-level waste glasses.

Description: The waste compo itions PW-7c and PW-9 were defined and glass development was completed. Major variations in major oxide concentration would not grossly affect the leach rates of the glass. Impact and strength tests on nonradioactive glass showed that the waste glasses produced slightly less fine particulate than commercial glass. Waste glass had 60% of the strength of the soda-lime glass. A water-quench reduced thermal conductivity about 20%, and a 24-h hold at devitrification temperatures did … more
Date: June 1, 1978
Creator: Ross, W.A.; Bradley, D.J. & Bunnell, L.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Overview of contamination from US and Russian nuclear complexes

Description: This paper briefly compares the United States and Russian weapons complexes and provides a perspective on the releases of radioactivity to the environment in both countries. Fortunately, the technologies, data, models, and scientific experience that have been gained over the last 50 years are being shared between the US Department of Energy (DOE) and Ministry of Atomic Energy of the Russian Federation (MINATOM) which constitutes a new environmental partnership between the two countries.
Date: June 1, 1995
Creator: Bradley, D.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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