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Regulatory analysis on emergency preparedness for fuel cycle and other radioactive material licensees. Draft report for comment

Description: Potential accidents for 15 types of fuel cycle and other radioactive material licensees were analyzed. The most potentially hazardous accident, by a large margin, was determined to be the sudden rupture of a heated multi-ton cylinder of UF/sub 6/. Acute fatalities offsite are probably not credible. Acute permanent injuries may be possible for many hundreds of meters, and clinically observable transient effects of unknown long term consequences may be possible for distances up to a few miles. Th… more
Date: June 1, 1985
Creator: McGuire, S.A.
Partner: UNT Libraries Government Documents Department
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Isotopic power materials development. Quarterly progress report for period ending December 31, 1976

Description: Research progress is reported on: (1) high-temperature alloys for space isotopic heat sources; (2) physical and mechanical metallurgy of heat source containment materials; (3) /sup 144/Cm fuel development; (4) terrestrial radioisotope applications; (5) selenide isotope generator system support; (6) isotope Brayton system materials support; and (7) space nuclear flight systems hardware. (TFD)
Date: June 1, 1977
Creator: Schaffhauser, A. C.
Partner: UNT Libraries Government Documents Department
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Irradiation effects on borosilicate waste glasses

Description: The effects of alpha decay on five borosilicate glasses containing simulated nuclear high-level waste oxides were studied. Irradiations carried out at room temperature were achieved by incorporating 1 to 8 wt % /sup 244/Cm/sub 2/O/sub 3/ in the glasses. Density changes and stored-energy build-up saturated at doses less than 2 x 10/sup 21/ alpha decays/kg. Damage manifested by stored energy was completely annealed at 633/sup 0/K. Positive and negative density changes were observed which never ex… more
Date: June 1, 1980
Creator: Roberts, F.P.
Partner: UNT Libraries Government Documents Department
open access

Interaction of radionuclides with geomedia associated with the Waste Isolation Pilot Plant (WIPP) site in New Mexico

Description: A survey of the potential of geological media from the vicinity of the Waste Isolation Pilot Plant site in Southeastern New Mexico for retardation of radionuclide migration in an aqueous carrier was conducted. The survey included the measurement of sorption coefficients (Kd) for twelve radionuclides between three natural water simulants and ten samples from various geological strata. The nuclides included /sup 137/Cs, /sup 85/Sr, /sup 131/I, /sup 99/Tc, /sup 125/Sb, /sup 144/Ce, /sup 152/Eu, /s… more
Date: June 1, 1978
Creator: Dosch, R.G. & Lynch, A.W.
Partner: UNT Libraries Government Documents Department
open access

Results from Nevada Nuclear Waste Storage Investigations (NNWSI) Series 3 spent fuel dissolution tests

Description: The dissolution and radionuclide release behavior of spent fuel in groundwater is being studied by the Yucca Mountain Project (YMP), formerly the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. Specimens prepared from pressurized water reactor fuel rod segments were tested in sealed stainless steel vessels in Nevada Test Site J-13 well water at 85{degree}C and 25{degree}C. The test matrix included three specimens of bare-fuel particles plus cladding hulls, two fuel rod segments wit… more
Date: June 1, 1990
Creator: Wilson, C. N.
Partner: UNT Libraries Government Documents Department
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