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Data Processing For Bubble Chambers

Description: The computer program which performs spatial reconstruction of events photographed in a bubble chamber is required to eliminate human and digitizer errors. It recognizes and corrects for single nuclear scatterings in the presence of multiple Coulomb scatterings. Momentum components are determined and kinematic constraints are applied. Measured parameters are performed into special reference frames and quantities of physical interest are calculated. Results are stored in a tape file containing al… more
Date: November 10, 1960
Creator: White, Howard S.
open access

Plasma Accumulation in a Device Fed by Energetic Ion Trapping

Description: Simon (1960) has given a general steady state theory of plasma accumulation (without energy losses) in an OGRA device. Such a device is fed by injection of energetic molecular ions which dissociate to produce trapped protons. Initial trapping is achieved by dissociation in the background gas. Such a device is usually characterized by a critical input current of critical plasma density (a function of input current) above which plasma density builds up to a value limited by Coulomb-scattering los… more
Date: November 10, 1960
Creator: Mackin, R. J., Jr.
open access

Evaluation of Commercial Ceramic Coating for Short Time Protection of Columbium 1% Zirconium

Description: Abstract. Fourteen commercial enamel frits from five different manufacturers were tested to determine their abilities to protect Nb-1% Zr during the forging cycle in the temperature range of 1800 to 2300 deg F. One frit was found to afford good coverage and protection at 2200 deg F at times up to 5 hours of exposure. Adherence was excellent during upset forging of a coated Nb--1% Zr sample heated 45 minutes at 2200 deg F. Another frit afforded good protection and coverage at 1700 deg F. (auth)
Date: October 10, 1960
Creator: McGrath, D. W.
open access

EGCR Lattice Radial and Angular Power Distribution 2.6 w/o Enrichment

Description: The measurements reported here are companion measurements to those reported earlier in HW-63585. The only significant difference between the measurements is that 1.8 w/o enrichment UO2 fuel was used for the first set, and 2.6 w/o enrichment UO2 fuel was used for the measurements described in this report. The new results will be presented graphically, and for completeness, the details of the measurement will be included here as well as in HW-63585.
Date: May 10, 1960
Creator: Nichols, P. F.
open access

Quarterly Report- January, February, March 1959 Plutonium Fuels Development Plutonium Metallurgy Operation

Description: Four capsules containing Al-1.65 w/o Pu and Al-12 w/o Si-1.65 w/o Pu were charged into the MTR. These capsules will be irradiated to a burnup of 80-100% of the plutonium atoms to determine the stability of the material at high exposures. An additional sixteen capsules containing 5 to 20 w/o Pu in Al and Al-Si have been prepared. Eight are awaiting reactor space and should be charged soon. The remaining eight are being recanned to increase the end gap between the core and the can. Also four caps… more
Date: May 10, 1960
Creator: Wick, O. J.; Thomas, I. D.; Stewart, R. W.; Stewart, R. W. & Nelson, T. C.
open access

Unclassified Research and Development Programs Executed for the Division of Reactor Development and the Division of Research April 1960

Description: A 19-rod Zircaloy-clad half-length PRTR spike element successfully irradiated to high plutonium burnout at full power in the ETR shoved partial bonding of the core and cladding. Unsatisfactory autoclave films on the Zircaloy cladding of the PRTR Al-Pu fuel elements are delaying final assembly of the first 30 clusters. Further conditioning of the autoclaves and the availability of permanent etching facilities are expected to correct the present difficulties.
Date: May 10, 1960
Creator: Hanford Laboratories Operation Irradiation Procesing Department
open access

The Preparation of Plutonium Powder by a Hydriding Process--Initial Studies

Description: Powder metallurgy is rapidly gaining importance as a means of fabricating nuclear fuel elements and other reactor components. It provides a convenient method for forming metals, unusual combinations of metals, and metal-ceramic combinations. The unique features of this technique which make it desirable for nuclear engineering purposes are the following:
Date: March 10, 1960
Creator: Stiffler, G. L. & Curtis, M. H.
open access

Gas-Graphite Reactions. I. Thermal and Microwave Oxidation of Various Reactor-Grade Graphites*

Description: Thermal oxidation of graphite in flowing CO2 is being studied at 650 to 850 C, in a single-pass gas system at atmospheric pressure, by observing weight loss rates. The method is used to provide comparative data for candidate reactor graphites. The effects on oxidation rates of graphite purity, structure, coke type, graphitization temperatures and other manufacturing variables are determined. In addition, the effects of gas flow rates and graphite surface to volume ratios are observed.
Date: February 10, 1960
Creator: Clark, T. J.
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