Search Results

Advanced search parameters have been applied.
open access

AN INFORMATION STORAGE AND RETRIEVAL SYSTEM FOR IRRADIATION EFFECTS IN METALS

Description: An information storage and retrieval system (PIC) was developed, utilizing the IBM 7090 computer, for handling data pertaining to the effects of neutron irradiation on metals. The input includes a reference identification, an appropriate abstract or extract summarizing the article, code identification parameters analogous to those used by the ASM-SLA Literature Classification System, and special codes identifying relevant irradiation and testing parameters. The output contains the same data plu… more
Date: August 15, 1963
Creator: Bush, S. H.
Partner: UNT Libraries Government Documents Department
open access

INVESTIGATION OF THERMAL-STRESS-FATIGUE BEHAVIOR OF STAINLESS STEELS. Quarterly Technical Progress Report, April-June 1962

Description: Activities in a program to obtain data on thermal-stressfatigue in various stainless steels under reactor conditions are reported. Information concerning procurement of equipment and materials is given along results of initial testing. A specimen of 304 stainless steel was strain-rate tested at 100 to 900 deg C. The averaged result of this test was 0.0005 in./in.-sec. Tensile testing of standard ASTM 1/2-in.-dia stainless steel rods is underway. Data obtained so far in the program are compared … more
Date: October 31, 1963
Creator: Horton, K. E.
Partner: UNT Libraries Government Documents Department
open access

Chloride Deposition From Steam Onto Superheater Fuel Clad Materials

Description: Experimemts using Cl/sup 36/ in a steam test loop were conducted to study the deposition behavior of chlorides on BONUS superheater fuel assembly materials. The moisture content of the steam was varied between 0 and 0.5 wt%, and superheat was added up to 15 deg F before the steam passed over the test cartridge heater. The effects of vaiiables on the chloride deposition on the heater were studied in detail. Chloride deposition from moist steam was found to result in heavy, adherent deposits whic… more
Date: October 18, 1963
Creator: Bevilacqua, F. & Brown, G. M.
Partner: UNT Libraries Government Documents Department
open access

INSTRUMENT FOR DETERMINING CRUSHING STRENGTH OF PARTICLES

Description: An instrument for crushing-strength determinations of uncoated and pyrolytic-carbon-coated fuel particles (50 to 500 mu in diameter) was developed to relate the crushing strength of the particles to their fabricability. The instrument consists of a loading mechanism, load cell, and a power supply-readout unit. The information that can be obtained by statistical methods of the data analysis is illustrated by results on two batches of fuel particles. (auth)
Date: November 29, 1963
Creator: Hallerman, G. & Gray, R.J.
Partner: UNT Libraries Government Documents Department
open access

Out-of-Pile Properties of Mixed Uranium-Plutonium Carbides. Progress Report, February 6, 1962-October 31, 1962

Description: Fabrication studies to produce high density solid solutions of 80% UC-- 20% RaC, with reproducible structure, composition, and density, were completed. Two types of material were produced: (U/sub 0.8/Pu/0.2/)C/sub 0.95/, single-phase monocarbide pellets with average densities of 12.8 g/cm/sup 3/ (94% of theoretical), sintered at 1950 deg C; and (U/sub 0.8/Pu/0.2/) C/sub 0.95/ + 0.1 wt% Ni sintering aid, major monocarbide and minor amount of sesquicarbide pellets, with average densities of 13.1 … more
Date: September 18, 1963
Creator: Strasser, A.; Stahl, D. & Taylor, K.
Partner: UNT Libraries Government Documents Department
open access

Out-of-Pile Properties of Mixed Uranium-Plutonium Carbides. Final Report

Description: Fabrication studies to produce high density solid solutions of 80% UC-- 20% PuC, with reproducible structure, composition, and density, were completed. Solid solution (U,Pu)C powder was produced by the oxide-carbon reaction, and the powders were consolidated by cold pressing and sintering. The studies were a continuation of work performed on Contract AT(30-1)-2899 with the USAEC. Two types of material were produced: 1. (U/sub 0.8/Pu/sub 0.2/)C/sub 0.95/, single,phase monocarbide pellets with av… more
Date: December 1, 1963
Creator: Stahl, D.; Strasser, A.; Taylor, K. & Anderson, J.
Partner: UNT Libraries Government Documents Department
open access

Materials tasks for LCRE, SNAP-50/SPUR, and advanced materials programs

Description: Declassified 30 Aug 1973. 125 figures are included which were presented at the Materials Review Meeting for the LCRE, SNAP-50/SPUR, and Advanced Materials programs, held at CANEL on Sept. 18 and 19, 1983. Fuels, structural materials. alkali metal coolants, and auxiliary materials are included. (DLC)
Date: September 27, 1963
Partner: UNT Libraries Government Documents Department
open access

Investigation of Thermal-Stress-Fatigue Behavior of Stainless Steels. Quarterly Progress Report No. 4, October-December 1962

Description: The thermal-stress-fatigue and strain-cycling-fatigue testing of Types 304 and 304-L stainless steels are discussed. The test variables included atmospheric surroundings, hold time, specimen size, and mean temperature. Results indicated a significant difference in fatigue life between annealed and cold-worked material. No significant difference in fatigue life resulted from testing in argon as opposed to air. Metallographic structural analysis showed the effects of strain softening as well as v… more
Date: October 31, 1963
Creator: Horton, K. E. & Stewart, R. S.
Partner: UNT Libraries Government Documents Department
open access

Ceramics Research and Development Operation Quarterly Report, October- December 1962

Description: CERAMICS RESEARCH AND DEVELOPMENT OPERATION QUARTERLY REPORT, OCTOBERDECEMBER 1962. Pu/sub 2/S/sub 3/ melted congruently at 1725 450 deg C in a 10 un. Concent 85% C under vacuum or argon and was stable to 2300 un. Concent 85% C in argon. Pu/sub 2/S/sub 3/ was not attacked by boiling, demineralized water. PuN melted congruently at 2750 450 deg C in a 75 un. Concent 85% C under nitrogen (1 atm), but dissociated at 2600 un. Concent 85% under argon or helium. Plutonium carbides and oxides of variou… more
Date: October 31, 1963
Partner: UNT Libraries Government Documents Department
open access

Corrosion Characteristics of the Rare Earth and Yttrium Metals

Description: The corrosion of rare earth metals in air, water, and aqueous solutions at different temperatures was measured by conventional weight-loss and weight- gain tests. The metals oxidize slowly in air, corrode slowly in water and alkaline solutions, and are readily soluble in most acids. Correlations of corrosion behavior with the electronic and physical properties of the rare earths are discussed. (auth)
Date: October 31, 1963
Creator: Lee, L. & Greene, N. D.
Partner: UNT Libraries Government Documents Department
open access

IN-PILE RADIATION CORROSION EXPERIMENTS WITH ZIRCONIUM, TITANIUM, AND STEEL ALLOYS IN 0.17 m UO$sub 2$SO$sub 4$ SOLUTIONS AT 280 C

Description: In-pile loop experiments L-2-15 and L-4-16 were designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO/sub 2/SO/sub 4/ solutions. The solutions employed were 0.17 m UO/ sub 2/SO/sub 4/, 0.015 m CuSO/sub 4/, and 0.03 m H/sub 2/SO/sub 4/ in H/sub 2/O for experiment L-2-15, and 0.17 m UO/sub 2/SO/sub 4/, 0.015 m CuSO/sub 4/, and 0.025 m H/sub 2/SO/sub 4/ in H/sub 2/O for experiment L-4-16. The mainstream temperature in the experiments ranged … more
Date: July 10, 1963
Creator: Jenks, G.H. & Baker, J.E.
Partner: UNT Libraries Government Documents Department
open access

Post-Irradiation Evaluation of a Plate-Type UO$Sub 2$ Fuel Element

Description: The premature failure of fuel Element M22, which had six compartments of 0.100-in.-thick, 96% TD UO/sub 2/ + 6 wt% ZrO/sub 2/ fuel, was attributed to the large irradiation-induced solid volume swelling of the UO/sub 2/ fuels. This volume swelling was the result of incomplete homogenization during fabrication of the mixed and sintered U/sup E/O/sub 2/ and U/sup N/O/sub 2/ fuel s in Element M22. In addition, heavy hydriding of the Ni-free Zircaloy-2 cladding occurred in the relatively hot areas a… more
Date: January 1, 1963
Creator: Meieran, H. B.
Partner: UNT Libraries Government Documents Department
open access

INVESTIGATION OF THERMAL-STRESS-FATIGUE BEHAVIOR OF STAINLESS STEELS. Quarterly Progress Report No. 6, April-JunE 1963

Description: A study was made of the effects of specimen size and grain size on thermal-stress-fatigue (TSF) behavior of stainless steels. The competing nature of failure by specimen instability and failure by fatigue was disclosed and shown to be a complex problem. It was shown also that conventional fatigue results and TSF results conform for 304-L stainiess steel for the variables studied. The testing of 304 and 304-L austenitic stainless steels, was essentially completed. The variables investigated in T… more
Date: October 31, 1963
Creator: Horton, K. E.
Partner: UNT Libraries Government Documents Department
open access

Electron Beam Melting of Uranium

Description: Feed stock prepared from ingot, dingot, and under-saltmelted U was melted by electron bombardment. Analysis of the ingots produced revealed that some Al, Cr, Mg, Mn, and Pb were volatilized from the melt. C was reduced when Zr was present in the feed material. H/sub 2/ and N/sub 2/ also were removed, the latter oniy when there was a relatively high concentration in the feed material. The work indicated the need for very slow melting rates or the casting of large diameter ingots for successful r… more
Date: June 14, 1963
Creator: Eikenberry, H. M.
Partner: UNT Libraries Government Documents Department
open access

INVESTIGATIONS OF CARBIDES AS CATHODES FOR THERMIONIC SPACE REACTORS. Quarterly Progress Report for the Period Ending May 31, 1963

Description: Two long-term test cells were fabricated and tested. One was loaded with a 30 UC--70 ZrC sample and the other with a 90 UC--10 ZrC samrple. The rates of vaporization of these samaples in vacuum were determined both in the absence and in the presence of a Ni anode maintained at 983 deg K with an electrode spacirig of 20 mils, hr order to set the baseline values. Measurement of the rates of vaporization of these samples under these conditions in the presence of Cs vapor at a pressure of about 1.8… more
Date: September 25, 1963
Partner: UNT Libraries Government Documents Department
open access

Outgassing Characteristics of Various Graphites

Description: The outgassing characteristics of various graphites have been determined in vacuo to a maximum temperature of 1000 deg C using external resistance heating and to 1800 deg C by induction heating. The graphites examined include commercial and experimental lots of nuclear grades prepared from different sources of raw materials and subjected to varying manufacturing procedures. The ash content of the various grades ranges from approximates 5 to approximates 800 ppm and the calcium content from a fe… more
Date: March 1, 1963
Creator: Overholser, L. G. & Blakely, J. P.
Partner: UNT Libraries Government Documents Department
open access

Corrosion of Stainless Steel in Acidic Nitrate Waste Solutions From Processing Stainless Steel Reactor Fuels

Description: The influence of the surface state on steel corrosion in high temperature steam and water is studied. The autoclave tests were continued for stainless steel grade 304 and undertaken for Creusot 1.2 MD07 boilerplate steel. Regarding the stainless steel, complete results for the tests in water at 300 deg C and partial results for the tests in steam at 400 deg C--200 kg/cm/sup 2/ are presented. The evaluation of the corrosion by ponderal variations involves the reduction of the adhering oxides by … more
Date: October 16, 1963
Creator: Hess, D. N.; Rice, L.; Willis, B.; Snavely, E. S. & Clark, W. E.
Partner: UNT Libraries Government Documents Department
open access

Development of a High Yield 90 Zr-10 U Alloy Massive Hydride

Description: Through addition of approximaely 0.4 wt % carbon (as zirconium carbide) to a 90 wt % Zr - 10 wt % U alloy, a 100% yield of uncracked massively hydrided fuel elements of high hydrogen density (N/sub/H ≈ 5.7 to 6.6) was obtained. The marked increase in yield was attirbuted t the presence of a carbide phase, serving as a nucleant and grain-growth inhibitor during solidification and subsequent solid-state transformations that occur during the hydriding process. The resulting hydride structure was f… more
Date: January 1, 1963
Creator: Raymond, J.W.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen