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Research and Development Reports for Sodium to Sodium Intermediate Heat Exchanger and Sodium to Water Steam Generator

Description: Results are presented of research and development work performed in conjunction with the 70-Mw design of a sodium-to- sodium intermediate heat exchanger and a sodium-to-water steam generator. Kanigen plating was substituted for Inconel overlays. A program to evaluate this plating was undertaken. Elimination of tube end ferrules, mechanical behavior of sine wave tubes, tube-to- tube sheet welded connections, metallurgical examination of bimetallic tubes, transition weld test, bayonet tube test, … more
Date: October 30, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MOLYBDENUM AND MOLYBDENUM-BASE ALLOYS. PART 1. HIGH-TEMPERATURE PROPERTIES OF A MOLYBDENUM-3 PER CENT THROIUM ALLOY. PART 2. EVALUATION OF A COLUMBIUM-ZIRCONIUM-TITANIUM CLADDING ALLOY

Description: In the first section of this report, a study was made of the high- temperature properties of a Mo-3% Th alloy to determine whether this alloy should be rejected as valueless or a full research program should be proposed. Results of this investigation show that thorium should be studied more intensively as an alloying addition for molybdenum. In the second section, an evaluation is presented of the oxidation behavior, mechanical properties, and cladding properties of Nb - 55 at.% Zr - 5 at.% Ti … more
Date: September 1, 1960
Creator: Rengstorff, G. W. P.; Root, G. S.; Holden, F. C. & Jaffee, R. I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Test of a Natural-Circulating High-Pressure Recombiner for Hydrogen and Oxygen

Description: A natural-circulation loop to catalytically recombine hydrogen and oxygen at high pressure was built and operated without incident. Stoichiometric 2H/sub 2/ + O/sub 2/ electrolytically generated from 15% KOH at high pressure, was recombined on platinized wire mesh at a rate of 0.60 to 0.75 scfm at 350 deg C aad 1500 psi total pressure for a period of 2500 hours. The concentration of stoichiometric gas ranged up to 8 mol%, the diluent being steam and excess O/sub 2/. Metallurgical examination of… more
Date: May 1, 1960
Creator: Hannaford, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. A Topical Report on SUB-SURFACE COATINGS FOR FUELED GRAPHITE SPHERES

Description: An exploratory program on subsurface coatin8s for graphite fuel elements is summarized. A number of coatings with various melting points which could be located beneath the surface of a fueled graphite sphere were investigated. Of the materials with lower melting points. nickel and a special glass compound appeared to form continuous coatings when a hot-pressing technique was employed. Several materials with high melting points. such as Ti, Cr, and MoSi/sub 2/, showed some promise, even though p… more
Date: June 30, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF HIGH-STRENGTH NIOBIUM ALLOYS FOR ELEVATED-TEMPERATURE APPLICATIONS

Description: A study to improve the elevated-temperature strength of niobium by solloving has resulted not only- in greatly improved strengths at 1200 and 1470 deg F but also in the development of improved fabrication techniques for these alloys. The most important step in the fabric:ition procedure of niobium and niobium-base allows is the initial breakdown of the cast structure. The cast structure of 1.84 wt. 4 chromium, 3.21 wt.% chromium. 4.33 wt. ' zirconium, and 20.5 wt.% titanium-4.28 wt. = chromium … more
Date: February 22, 1960
Creator: De Mastry, J. A.; Shober, F. R. & Dickerson, R. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section B Monthly Progress Report, June-July 1960

Description: The effect of two neutron poisons, baron and cadmium, on the rate of dissolution of high-density 95% ThO/sub 2/-5% UO/sub 2/ pellets in the Zirflex Process was determined. Dissolution of U-10% Mo alloy in boiling HNO/sub 3/ resulted in a precipitation of uranyl molybdates. Air caused greater uranium and thorium losses during decladding of ThO/sub 2/-UO/sub 2/ fuel than irradiation. Processing of U-Mo fuel by a Zircex type process is discussed. Two leaches of graphitized fuel with 90% HNO/sub 3/… more
Date: December 12, 1960
Creator: Blanco, R E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Loading, Shipping and Testing Procedures for Task 2 Isotopic Powered Thermoelectric Generator. Preliminary Technical Manual

Description: A preliminary report on the operations and procedures for handling a 125- w thermoelectric generator and its isotopic heat source is presented. Full-scale mock-ups were used to develop the procedures. A cylindrical metal block of Inconel X will be remotely loaded with an isotope at ORNL. The block will then be sealed snd loaded into a specially designed cask and shipped by rail to the Martin nuclear hot cell facility, where the second phase of the operation will be conducted. (W.D.M.)
Date: March 24, 1960
Creator: Reilly, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tensile Properties of Yttrium-Titanium and Yttrium-Zirconium Alloys

Description: Complete series of yttrium-titanium and yttrium-zirconium alloys was tested in tension at room temperature. Ultimate tensile strength, yield strength, and reduction in area data are reported for the alloys. Yield point phenomena were encountered in both alloy systems. (auth)
Date: December 1, 1960
Creator: Bare, D. W.; Gibson, E. D. & Carlson, O. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion Status: Sulfex-Thorex (Ni-O-Nel) and Darex-Thorex (Titanium) as of June 12, 1959

Description: Current results indicate probable over-all rates of about 0.2 mils/month for titanium vs. 1.5 to 3.0 mils/month for Ni-o-nel. Tests are not 100% comparable due to changes made in flowsheet conditions, but they have been of sufficient variation and length as to allow good predictions to be made. Both metals show some tendency toward local attack in Thorex solutions. These tendencies are increased by poor welding techniques. There is a possibility that a Ni-onel dissolver could be used for interi… more
Date: June 29, 1960
Creator: Clark, W E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of Corrosion-Resistant Alloys for Use as Container Materials for Decladding Solutions or as Welding Alloys

Description: Twenty-four experimental alloys were developed and evaluated as container materials or welding alloys for use with Sulfex and Niflex decladding solutions. Niflex solutions which were more corrosive than Sulfex solutions to most of the experimental alloys, produced severe localized attack on weldments made on vacuum-melted Hastelloy F with the experimental alloys. However, several of the alloys, when self-welded, were not selectively attacked. Some of these showed a substantial improvement in re… more
Date: August 1, 1960
Creator: Peterson, Charles L.; Drennen, David C.; Langston, Merritt E.; Hall, A. M. & Boyd, Walter K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress Relating to Civilian Applications During September, 1960

Description: The study of possible reactions induced by the application of high pressures at high temperatures was concentrated on U/sub 3/O/sub 8/-Al/sub 2/O/ sub 3/. Data are reported on the effects of temperature on the tensile properties of fully recryatallized Cr-- Hb, Nb-- V, Nb-- Zr, and Cr-- Nb-- Zr alloys. The effect of radiation on the creep properties of Zircaloy-2 at elevated temperatures is being studied. Magnesium oxides are being evaluated as a fuel matrix material for uranium dioxide. Specim… more
Date: October 1, 1960
Creator: Dayton, R.W. & Tipton, C.R. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MEASUREMENT OF SURFACE AREA OF URANIUM DIOXIDE POWDER AND SINTERED PELLETS

Description: The surface areas of sintered uranium dioxide pellets (individual pellets ranging from 50 to 2000 cm/sup 2/) were measured with a precision of 1.3% and a reproducibility of about 4% with a BET adsorption apparatus, using krypton as the adsorbate. Powder samples (10 to 50 mg) of uranium dioxide, anatase, zirconia, and ceria were measured with a precision of 0.5% and a reproducibility of about 3%. An excellent correlation was found between the surface area and the average particle diameter, as me… more
Date: October 1, 1960
Creator: Smith, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of Corrosion-Resistant Niobium-Base Alloys

Description: The hot-water corrosion resistance and mechanical properties of niobium and a number of its alloys were evaluated relative to their usefulness in pressurized-water thermal reactors. Unalloyed niobium was found to be rapidly attacked by 600 and 680 deg F water and 750 F steam. A number of alloying additions were found which markedly improve the corrosion resistance of niobium. Of these, binary and ternary combinations of chromium, molybdenum, titanium, vanadium, and zirconium were among the most… more
Date: May 12, 1960
Creator: Maykuth, D. J.; Klopp, W. D.; Jaffee, R. I.; Berry, W. E. & Fink, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SYNTHESIS AND FABRICATION OF REFRACTORY URANIUM COMPOUNDS. Monthly Progress Report No. 11, November 1-November 30, 1960

Description: Batches of UC were synthesized for use in fabrication of specimens for physical property determinations. This synthesis was carried out with mixed loose powders in a graphite crucible. Two and one-half pound batches of UN were synthesized using a stainless steel boat and an Inconel muffle furnace. Three batches of U/sub 3/Si/sub 2/ were synthesized with particular emphasis on controlling the rate of the reaction by limiting the maximum temperature to 1500 deg C. In addition, determinations were… more
Date: December 13, 1960
Creator: Taylor, K. M. & McMurtry, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SNAP I--Dynamic Mercury Loop Tests of Selected Materials. Period Covered : January 1957-June 1959

Description: Six dynamic boiling-mercury loops were tested in connection with the SNAP-I program. The loops were Croloy-5 Si, Croloy-5 Ti, Carpenter 20 Nb, Types 347 and 446 stainless steel and a Type 347 stainless-steel-clad niobium boiler coil inserted into the Type 347 stainless-steel loop. Operation of the Croloy-5 Si loop was discontinued after about 86 hr because the heaters bured out. Extensive general corrosion which penetrated as much as 3.5 mils occurred during this time. The boiler-outlet leg of … more
Date: March 1, 1960
Creator: McGrew, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EXAMINATION OF CORROSION SPECIMENS FROM SLURRY BLANKET MOCKUP RUNS SM-6 THROUGH SM-9

Description: Low attack rates (0.1 to 0.5 mpy) were displayed by coupon specimens of type 347 stainless steel, titanium RC-55, and Zircaloy-2 which were exposed for 2877.5 hr in an oxygenated slurry of Th--8% U oxide, 116.5 hr in water, 6.9 hr in 5% HNO/sub 3/, and 4.3 hr in 3% triscdium phosphate during mns SM-6 through SM-9 in the slurry blanket mockup. The leading coupon of type 347 stainless steel showed a slightly higher rate than the other stainless steel ccupons due to entrance effects. Specimens of … more
Date: May 26, 1960
Creator: Gallaher, R B; Reed, S A & Warner, G G
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SNAP II REACTOR CORE MATERIALS

Description: A survey was made to select the construction materials for the SDR-1 reactor core vessel and grid plates. Hastelloy C was selected for the reactor vessel, top grid plate, and bottom grid plate. Inconel X was selected for the core hold-down springs. (C.J.G.)
Date: April 11, 1960
Creator: Facha, J. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hydrides of Titanium, Yttrium, and Zirconium: a Bibliography

Description: This bibliography contains 94 references on metal hydrides, with particular emphasis placed on the hydrides of titanium, yttrium, and zirconium. The bibliography covers the period 1955 through 1959. The references are arranged alphabetically by title. Sources used in compiling this bibliography are: Applied Science and Technology Index, Abstracts of Classified Reports, ASM Review of Metal Literature, Bibliographies of Interest to the Atomic Energy Program, Classified and Unclassified Parts, Ind… more
Date: April 28, 1960
Creator: Cernak, Elizabeth A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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