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Report of invention

Description: This invention discloses a method of making a synthetic nuclear fuel by mixing pure U-233 with U-238 fuels, such as depleted uranium, to produce a fuel that combines the most desirable nuclear properties of both the U-233 and U-238 fertile material. The process requires that U-233 be manufactured in such a manner as to be relatively uncontaminated from U-232. The subject of this invention is a method of fuel handling that incorporates the desirable features of both U-233 and U-238. It is propos… more
Date: January 23, 1963
Creator: Lang, L. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Space Vehicle Shielding Studies Calculations of the Attenuation of a Model Solar Flare and Monoenergetic Proton Beams by Aluminum Shields

Description: Using the straight-ahead approximation, nucleon-meson cascade calculations have been carried out for a typical proton flare spectrum incident on a shield and for approximately monoenergetic incident proton beams. The shield material considered has approximately the properties of Al. The results from the monoenergetic beams may be used to obtain shielding information for any incident proton spectrum. (auth)
Date: January 23, 1963
Creator: Alsmiller, R. G., Jr. & Murphy, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

REPORT OF THE QUALIFICATION TESTING OF SNAP 10A FIXED RESISTORS

Description: Upon completion of the initial visual examination and dimensional check, the resistors were weighed and the weights were recorded. The measurement of insulation resistance, performed with a megohmmeter, indicated infinity for each resistor. The dielectric strength test was performed with a high potential a-c dielectric strength tester. The test voltage was applied with no evidence of leakage or breakdown in any case. A wheatstone bridge was used to measure the d- c resistance of each resistor. … more
Date: January 23, 1963
Creator: Holtwick, J. S., III
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CONTINUOUS DISSOLUTION OF ZIRCONIUM REACTOR FUELS IN TITANIUM EQUIPMENT: LABORATORY DEMONSTRATION

Description: Continuous dissolution of 2% U-- Zr alloy fuel in a laboratory-scale Ti dissolver was demonstrated using refluxing 3 M HNO/sub 3/--1.2 M HF--0.4 M HBF/ sub 4/--0.6 M Cr(III)0.4 M Cr(VI)--0.46 M Zr as the dissolvent. Dissolution rates and solution corrosion rates were 8 to 16 mg/cm/sup 2/min and approximates 1 mil/month, respectively. Reagent was added to the dissolver at the rate needed to maintain the potential measured by a Au vs. calomel electrode in the product effluent as close to a presel… more
Date: January 23, 1963
Creator: Gens, T.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparison of Dialkyl Phenylphosphonates With Tri-N-Butyl Phosphate in Nitrate Systems: Extraction Properties, Stability, and Effect of Diluent on the Recovery of Uranium and Thorium From Spent Fuels

Description: Di-n-butyl phenylphosphonate (DBPP) and di-sec-butyl phenylphosphonate (DSBPP) were investigated as possible substitutes for tri-n-butyl phosphate (TBP), the reagent presently employed in the reprocessing of uranium and thorium nuclear reactor fuels. The phenylphosphonates form complexes with uranium and thorium that are mostly insoluble in the aliphatic solvents commonly used as diluerts for TBP but that are soluble in other diluert type, for example, aromatics and CCl/sub 4/. Therefore, the p… more
Date: January 23, 1963
Creator: Blake, C. A., Jr.; Gresky, A. T.; Schmitt, J. M. & Mansfield, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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