Technical Report Archive & Image Library (TRAIL) - 10 Matching Results

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Automatic Recording Unit

Description: From abstract: The PT-750 is designed to be used in conjunction with a production tester which requires automatic recording of test data. This manual provides a source of procedures and reference material necessary in automatic recording and in use of the PT-750.
Date: March 29, 1960
Creator: Ross, Frank A.
Partner: UNT Libraries Government Documents Department
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Bimetallic Casting

Description: "The purposes of the program being conducted under the present contract are: 1) To determine the feasibility of cladding zirconium on uranium by a direct casting process. 2) To investigate the diffusion of liquid metals in the fusion zone."
Date: March 29, 1961
Creator: Krashes, David
Partner: UNT Libraries Government Documents Department
open access

Design Criteria for Irradiated Vessels Task 6.0 Summary Report

Description: Abstract: This technical report presents design criteria to prevent the brittle fracture of ferritic reactor vessels that cold occur as a result of the rise in NDT caused by fast neutron irradiation. The criteria require that maximum principal stress in the vessel does not exceed 18 percent of yield stress at temperatures below NDT + 60 degree F. Under certain conditions the allowable stress may be based on the irradiated yield stress. A discussion of brittle fracture and an explanation of the … more
Date: September 29, 1961
Creator: McLaughlin, D. W.
Partner: UNT Libraries Government Documents Department
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The Development of Uranium Carbide as a Nuclear Fuel: Final Report

Description: From introduction: This is the final report on uranium carbide studies sponsored by the United States Atomic Energy Commission and performed by United Nuclear Corporation at its New Haven Research Laboratories during the period from May 1959 to January 1964. The work was part of the Commission's Fuel Cycle Development Program aimed at lowering the cost of nuclear power by improving fuel cycle technology. At the inception of this program in 1959, some work was in progress on uranium carbide. Lit… more
Date: February 29, 1964
Creator: Crane, J. & Gordon, E.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960

Description: From Summary: "The major objective of the run was the investigation of fuel stability. The reactor operated for long periods at the design power of 5 Mw with none of the usual indications of instability while the system pressure was kept at 1250 psig. Run 21 ended on January 22, so that the reason for an abrupt change in the mixing rate of fuel between the core and blanket could be investigated and a reactor steam-system valve could be repaired."
Date: April 29, 1960
Creator: Briggs, R. B.
Partner: UNT Libraries Government Documents Department
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Self-Diffusion in α-Iron During Compressive Creep

Description: "The influence of compressive creep on the self-diffusivity of α-iron has been measured in the temperature range of 742-885°C. the diffusivity is enchanced in proportion to the strain rate, but this dependence decreases with increasing temperature. The magnitude of the strain is relatively unimportant in this connection. Strain rates from 0 to -2 x 10¯³ sec¯¹ were investigated with a corresponding increase in diffusivity up to 3 x 10³ times. The results are analyzed in terms of vacancy diffu… more
Date: May 29, 1962
Creator: Hirano, Ken-ichi; Averbach, B. L. & Cohen, Morris
Partner: UNT Libraries Government Documents Department
open access

Special Power Excursion Reactor Test III Pressurizer Vessel Failure

Description: Report documenting results of a study of the cause of failure at the SPERT III reactor facility.
Date: January 29, 1962
Creator: Heffner, R. E.; Wilson, T. R.; Halls, D. P.; Hickman, W. W. & Hoopingarner, K. R.
Partner: UNT Libraries Government Documents Department
open access

Thermal Analysis of SM-1 Core III

Description: Abstract This technical report covers the thermal analysis performed on the SM-1 Core III for both steady state and transient conditions is reported. SM-1 Core III will be used as a test for Type 3 elements in a PM-2A Core. The steady state analysis indicated minimum departure from nucleate boiling ratios (DNBR) for both design and scram conditions above the minimum criteria of 1.5. Local nucleate boiling was noted in the hot internal channels and lattice passage at scram power conditions. Loss… more
Date: June 29, 1962
Creator: Davidson, S. L.
Partner: UNT Libraries Government Documents Department
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