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Role of Ionization in Radiation Annealing

Description: "The role of ionization in the phenomenon of 'radiation annealing' of graphite has been studied by using a 1-Mev electron beam. Changes in the c-axis of a sample with a Hanford irradiation of 460 mwd/ct were studied. Two thermal anneals of 4 hours each at 350 degrees C proved sufficient to complete the thermal annealing at this temperature. The samples were then irradiated for 7-1/2 hours at a temperature of 340 degrees C. The samples received an irradiation of 47 microampere-hours, equivalent to ionization to an exposure of 200 mwd/ct in a Hanford reactor. No changes were noted as a result of the electron bombardment. It is concluded that the ionization is ot of major importance in radiation annealing.
Date: October 1, 1954
Creator: McClelland, J. D.; Smith, A. W. & Senkovits, E. J.
Partner: UNT Libraries Government Documents Department
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Separations Chemistry, Quarterly Progress Report, April-June 1954

Description: "Scale-up experiments on high temperature fuel recovery processes have included the dummy run phase on the handling of 1-kologram samples of molten, non-irradiated uranium in the hot cell. The next step involves the use of spent X-10 fuel slugs. Small scale experiments with X-10 uranium on the extaction of Pu with Mg show that as much as 80 per cent of the Pu can be removed in pone pass. Treatment of uranium with fused fluorides can remove at least 90 per cent of the Pu in one pass. Oxide scavenging with ZrO2 is very effective in removing rare earths.:
Date: October 1, 1954
Creator: Bareis, David W.; Cubicciotti, Daniel D. & Motta, E. E.
Partner: UNT Libraries Government Documents Department
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Safety Evaluation of PNPF Modifications

Description: "The purpose of this report is to examine the safety aspects of PNPF restart on continued operation, after completion of the core cleanup and system modifications."
Date: May 1, 1969
Creator: Huntsinger, M. & Hart, R. S.
Partner: UNT Libraries Government Documents Department
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Annual Technical Progress Report, AEC Unclassified Programs: 1966

Description: Annual report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the 1965-66 fiscal year.
Date: August 31, 1966
Creator: North American Aviation. Atomics International Division.
Partner: UNT Libraries Government Documents Department
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Annual Technical Progress Report, AEC Unclassified Programs: 1965

Description: Annual report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the 1964-65 fiscal year.
Date: November 10, 1965
Creator: North American Aviation. Atomics International Division.
Partner: UNT Libraries Government Documents Department
open access

Carbide Fuels in Fast Reactors

Description: Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.
Date: September 15, 1965
Creator: Wheelock, C. W.
Partner: UNT Libraries Government Documents Department
open access

The High-Temperature Irradiation Behavior of Hypostoichiometric Uranium Monocarbide

Description: From abstract: A series of three multi-compartmented experiments was designed to investigate the irradiation behavior uranium carbide fuels, as a function of composition, temperature, and burn-up; and the mechanical properties of Type 304 stainless steel, as a function of temperature and integrated thermal neutron flux.
Date: August 31, 1965
Creator: Hahn, R. D.
Partner: UNT Libraries Government Documents Department
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SRE Heat Transfer System Demolition

Description: From introduction: This report details the extensive modifications to the SRE heat transfer systems required to accomplish increased capacity objectives.
Date: August 31, 1965
Creator: Nicholson, J. O.
Partner: UNT Libraries Government Documents Department
open access

U-10 Wt % Mo Fuel Element: Irradiation in SRE

Description: From abstract: The fuel element assembly was successfully irradiated in the SRE to a maximum burnup of 5300 Mwd/MTU, at a peak fission rate of approximately 1.5 x 10E13 fissions/cm3-sec and a maximum central temperature near 1200F.
Date: August 31, 1965
Creator: Arnold, J. L.; Miller, K. J. & Peterson, R. M.
Partner: UNT Libraries Government Documents Department
open access

Large SGR Control Rod Development

Description: From abstract: A development program was initiated to design, fabricate and test an absorber column with a 10 to 12 year lifetime, for use in the proposed LSGR.
Date: July 25, 1965
Creator: Dermer, M. D.
Partner: UNT Libraries Government Documents Department
open access

The Properties and Irradiation Behavior of U₃Si₂

Description: Abstract: A limited study of the compound U₃Si₂ has been made in reference to its use as a prospective nuclear fuel in sodium cooled reactors.
Date: July 25, 1965
Creator: Shimizu, H.
Partner: UNT Libraries Government Documents Department
open access

Calandria Core Weld Joint Development

Description: Abstract: The design and initial test of cutting and welding equipment developed to remotely cut and re-weld the bottom process tube joint are discussed in this report.
Date: June 30, 1965
Creator: Roberts, J. G.
Partner: UNT Libraries Government Documents Department
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