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APPR-1 HOT CHANNEL FACTORS. RE-EVALUATION ON THE BASIS OF MANUFACTURING EXPERIENCE AND ZERO POWER EXPERIMENTS
None
Date:
May 1, 1957
Creator:
Brondel, J.O.
System:
The UNT Digital Library
Aqueous Homogeneous Research Reactor--Feasibility Study
None
Date:
May 1, 1957
Creator:
Kasten, P. R.; Lundin, M. I.; Segaser, C. L.; Aven, R. E.; Gilfillan, D. R.; Hughes, R. F. et al.
System:
The UNT Digital Library
Chemical Engineering Division Summary Report
This report addresses the summary report of the Chemical Engineering Division.
Date:
May 1, 1957
Creator:
unknown
System:
The UNT Digital Library
DEVELOPMENT AND PROPERTIES OF URANIUM-BASE ALLOYS CORROSION RESISTANT IN HIGH TEMPERATURE WATER. PART IV. RADIATION STABILITY OF URANIUM-BASE ALLOYS
The effects of pile irradiations on the physical properties and corrosion resistance of U-- Mo, U-- Nb; and U--Si alloys are reported. The dimensional stability under irradiation of the gamma phase U-- Mo and U-- Nb alloys is excellent; however, an isotropic volume increase of 4 to 6% per wt.% burnup may limit the ultimate fuel element life. Corrosion resistance of the gamma-phase alloys appesrs to be improved when subjected to s neutron field; this is attributed to an irrsdiation induced stabilization of the gamma phases. The U/ sub 3/Si alloy, on the other hand, suffered severe deterioration, particularly of corrosion resistance. Changes in electrical resistivity, hardness, mechanical properties, and crystal structure are presented and the mechanisms producing the observed changes discussed. (auth)
Date:
May 1, 1957
Creator:
Bleiberg, M.L.; Eichenberg, J.D.; Fillnow, R.H. & Jones, L.J.
System:
The UNT Digital Library
Effects of High Burnup on Natural Uranium
None
Date:
May 1, 1957
Creator:
Kittel, J. H. & Paine, S. H.
System:
The UNT Digital Library
EVALUATION OF COATED Al$sub 2$O$sub 3$ AND TUNGSTEN CARBIDE BEARING-JOURNAL ASSEMBLIES IN WESTINGHOUSE 100A PUMP. Summary of Runs S-96A and S-97
None
Date:
May 1, 1957
Creator:
Kitzes, A.S. & McLaughlin, C.A.
System:
The UNT Digital Library
Fabrication of Dispersed Uranium Fuel Elements Using Powder-Metallurgy Techniques
Fabrication techniques for producing dispersion fuel elements with cores of 30 volume per cent of UC, U/sub 2/Ti, U/sub 3/Si, or U/sub 6/Ni dispersed in Zircaloy 2 and 30 volume per cent of UC or UN dispersed in Type 18-8 stainless steel have been investigated. Roll-clad plate-type elements of all these compositions may be fabricated by powdermetallurgy methods in such a manner that good core-tocladding bonds and cores with uniform dispersions of discrete uranium- compound particles are obtained. From the standpoint of fabricability, elements containing UC in Zircaloy 2, UC in stainless steel, and UN in stainless steel are the most promising. The UN in stainless steel has the best corrosion resistance in 680 deg F degassed water; however, UC in stainless steel has the best resistance to corrosion in 700 deg F NaK. (auth)
Date:
May 1, 1957
Creator:
Paprocki, S. J.; Keller, D. L. & Cunningham, G. W.
System:
The UNT Digital Library
IRRADIATION OF CAST URANIUM-PLUTONIUM BASE ALLOYS. Final Report-- Metallurgy Program 6.5.4
None
Date:
May 1, 1957
Creator:
Smith, K.F. & Kelman, L.R.
System:
The UNT Digital Library
Pressure Vessel and Piping Codes Applicable to the PWR Reactor Plant
State, Government, and ASME Codes are given for the radistion exposure, waste disposal, piping, and pressure vessels for the PWR reactor plant. (W.L.H.)
Date:
May 1, 1957
Creator:
Dobinsky, J. F.; Andrew, M. B. & Moffette, T. R.
System:
The UNT Digital Library
PROCESS DEVELOPMENT QUARTERLY REPORT. II. PILOT PLANT WORK
Progress is reported on the gross solubility of U in digestions of Mallinokrodt feed materials, studies of variables affecting U purity in a TBP hexane extraction cycle, low-acid flowsheet for TBP--hexane extraction process based on a 440 g U/liter in lM HNO/sub 3/ digest liquor, hacking studies in the pilot plant pumperdecanter system, recovery of U from residues from the dingot process, lowering the H level in dingot metal, forging of dingot bar stock, dingot extrusion, fubrication of UO/sub 2/ fuel elements, and the determination of H content of derby and ingot metal. (W.L.H.)
Date:
May 1, 1957
Creator:
Kuhlman, N. ed.
System:
The UNT Digital Library
RATE OF GROWTH OF DIFFUSION LAYERS IN U-Al AND U-AlSi COUPLES
The rates of growth of diffusion layers between U and Al and between U and AlSi alloy (eutectic composition) were studied and compared over the temperature range 250 to 55O deg C. Metallographic observation shows that the U-- Al reaction layers form three to five times as fast as the U-- AlSi layers over this temperature range. Sixty per cent of the layer growth takes place in the Al or AlSi alloy and 40% in U. (auth)
Date:
May 1, 1957
Creator:
DeLuca, L.S. & Sumsion, H.T.
System:
The UNT Digital Library
Reactor Safety Bibliography. Selected Unclassified References
This is a revision of the Reactor Safety Bibliography prepared for the Reactor Safety Conference held at New York City on Oct. 31, 1957. It is not an exhaustive review of the published material on reactor safety but includes 223 selections from reports and published literature as a guide to some of the more recent and relevant material. (J.E.D.)
Date:
May 1, 1957
Creator:
unknown
System:
The UNT Digital Library
SELECTED PROPERTIES OF VANADIUM ALLOYS FOR REACTOR APPLICATION
None
Date:
May 1, 1957
Creator:
Smith, K.F. & Van Thyne, R.J.
System:
The UNT Digital Library
STUDIES OF PARTICLE SIZE DISTRIBUTION IN FLUIDIZED BEDS
None
Date:
May 1, 1957
Creator:
Katz, H.M.
System:
The UNT Digital Library
The Theoretical Physics of the Argonaut Reactor
None
Date:
May 1, 1957
Creator:
Kelber, C. N.
System:
The UNT Digital Library
Thermodynamics of Sodium Tetramethoxyborate and Tetramethoxyborate Ion
None
Date:
May 1, 1957
Creator:
Coulter, L. V.; Sinclair, J. R. & Haddaway, M. G.
System:
The UNT Digital Library
Two-Group Analysis of Thermal, One-Dimensional, Multi-Region Spherical Reactors
This technical report described the formulation of a set of two-group neutron diffusion equations and the solution for the critical fuel cross section in a one-dimensional, multi-region spherical reactor. A subsequent report will describe the ORACLE code developed for survey calculations using this method.
Date:
May 1, 1957
Creator:
Nestor, C. W.
System:
The UNT Digital Library
Valve Operating System System Description No. 10
A description is given of the valve operating system for the PWR. The valves served by this system are a component pant of the following systems: reactor coolant system; pressurizer and pressure relief system; coolant discharge and vent system; and failed element detection and location system. (W.L.H.)
Date:
May 1, 1957
Creator:
unknown
System:
The UNT Digital Library