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Hanford Works Monthly Report: January 1952
This is a progress report of the production reactors on the Hanford Reservation for the month of January 1952. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.
Date:
February 21, 1952
Creator:
Prout, G. R.
System:
The UNT Digital Library
HYDRODYNAMIC STUDIES IN THREE GLASS MODELS
None
Date:
October 21, 1952
Creator:
Lesem, L B
System:
The UNT Digital Library
Irradiation of 63S Aluminum Samples
Data obtained from testing and observing samples of 63S Al irradiated for approximately three months are presented. Tensile data show a slight, general increase in strength during pile exposure with a slight decrease in elongation. It is uncertain whether tkis increase in strength is a result of irradiation, exposure to slightly elevated temperatures, or a combination of the two effects. Metallographic examination revealed no apparent damage to the microstructure. As a result of these tests. it was determined that there is no daruage in the 63S Al samples caused by irradiation. (auth)
Date:
August 21, 1952
Creator:
Wright, P. D.
System:
The UNT Digital Library
Metallurgy Division Quarterly Progress Report for Period Ending October 31, 1951
Eleven thorium-carbon alloys in the range 0.02 to 2.0% carbon were prepared by vacuum-arc melting. The hardness varied from 19 R/sub A/ for the 0.02% alloy to 108 R/sub B/ for the 2.0% alloy. The preparation of thorium- chromium alloy was hampered by a reaction with the zirconia molds, which results in porosity in the casting. The failure of aluminum-silicon bonded X-10 slugs after heat treatment for seven days at 400 deg C was traced to the failure to remove tin after the tin dip and the presence of a gas during heat treatment. Tensile tests were made on extruded thorium, and no correlation was found with extrusion variables. A composition effect was found, however, which showed a linear relationship between carbon content and tensile strength. Creep tests on thorium, uranium, and Inconel continue. The program of evaluating the variables in the fabrication of clad fuel elements, using MTR techniques was concerned mainly with the distribution of UO/sub 2/ in the core compact, the temperature of rolling, and the particle size of the metallic core powder. Progress is being made in the preparation of three-layer laminates without the use of a protective can during the hot-rolling operation but with the …
Date:
April 21, 1952
Creator:
Bridges, W.H. ed.
System:
The UNT Digital Library
Production test 234-5-2-MS, Evaluation of the A331 crucible or modification thereof for routine use as a reduction crucible on the remote mechanical line
None
Date:
October 21, 1952
Creator:
Hay, John M
System:
The UNT Digital Library
Sampling Methods and Requirements for Estimating Airborne Radioparticulate Hazards
None
Date:
November 21, 1952
Creator:
Burnett, T. J.
System:
The UNT Digital Library
SCOPE OF P.B.R. STUDY
None
Date:
November 21, 1952
Creator:
Zmola, P C
System:
The UNT Digital Library
Summary of the Research Progress Meeting of July 24, 1952
None
Date:
August 21, 1952
Creator:
Shewchuck, Sergey
System:
The UNT Digital Library
THE THERMODYNAMICS OF THE REDUCTION OF URANIUM COMPOUNDS TO URANIUM METAL
None
Date:
July 21, 1952
Creator:
Lemmon, A.W.; Ward, J.J.; Fischer, S.M.; Geankoplis, C.J. & Clegg, J.W.
System:
The UNT Digital Library