Search Results

open access

In-Pile Test of Prototype ML-1 Fuel Elements

Description: Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.
Date: June 1964
Creator: Brunhouse, J. S.; Burgess, A. B.; Geering, G. T.; Nakazato, S. & Titus, G. W.
Partner: UNT Libraries Government Documents Department
open access

Effect of high temperature in-pile irradiation upon high density UO/sub 2/ bodies

Description: As a part of the ML-1 fuel evaluation program, high density bulk UO/sub 2/ pellets were irradiated to burnups equivalent to 8500 hours of ML-1 reactor operation (3.0 a/o U-235) under temperature conditions approximating those expected in the reactor (1750/sup 0/F peak cladding surface temperature). Post irradiation examination revealed severe fuel cracking although fission product gas release measurements agreed well with calculated values. No structural changes were revealed by metallography a… more
Date: January 1, 1977
Creator: Saling, J. W. & Titus, G. W.
Partner: UNT Libraries Government Documents Department
open access

HIGH-TEMPERATURE IRRADIATION OF UO$sub 2$-BeO BODIES

Description: As a part of the ML-1 reactor fuel evaluation program, UO/sub 2/-- BeO bodies containing two UO/sub 2/ compositions, 70 and 80 wt% UO/sub 2/, were irradiated to a burnup equivalent to 8750 hours of ML-1 reactor operation (8.5% U/ sup 235/). It was estimated that maximum cladding surface temperatures of 1710 nif- F were attained during irradiation. Reference design burnup for the ML-1 is 9.7% U/sup 235/, in 10,000 hours of operation at maximum clad surface temperatures of 1750 nif- F. Postirradi… more
Date: January 1, 1963
Creator: Titus, G. W. & Saling, J. H.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen