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Camden-Delaware Valley Area (ARMS-II)

Description: Report regarding an Aerial Radiological Measuring Survey (ARMS) of the Camden-Delaware Valley area that was part of a national program to measure environmental levels of gamma radiation. 6,000 traverse miles were examined around Camden, New Jersey.
Date: November 10, 1961
Creator: Guillou, R. B.
Partner: UNT Libraries Government Documents Department
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Bibliography and Index on Vacuum and Low Pressure Measurement

Description: From Introduction: "This paper consists essentially of a) a bibliography, b) an author index, and c) an index of the subject matter of the bibliography. While the primary objective is to focus on vacuum measurement, it was believed essential to include in the bibliography articles on vacuum technology in some measure accessory or essential to vacuum measurement. For maximum usefulness, an index of the subject matter of the references has been prepared. The abstract publications listed in the previous paragraph have been freely drawn upon in preparing the bibliography."
Date: November 10, 1961
Creator: Brombacher, W. G.
Partner: UNT Libraries Government Documents Department
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Critical Path Scheduling in Maintenance

Description: Summary: The following narrative interspersed with figures and attached reference exhibits is designed to acquaint the reader with the scheduling procedure developed at ORGDP, trial results and evaluation, subsequent improvement, further application, and use in conjunction with our IBM 7090 Computer.
Date: April 10, 1961
Creator: Gritzner, C. L.; Jones, J. P. & Ellis, J. M.
Partner: UNT Libraries Government Documents Department
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Examinations of Pump Impellers From Sodium and Fused Salt Pump Endurance Tests

Description: Examinations of three Inconel pump impellers were made to establish the extent of cavitation damage and degree of carburization sustained during pump endurance tests. The pumps, two of which circulated fluoride salt and one sodium, operated for the bulk of the test programs in the temperature range 1000 to 1250 deg F. Cavitation damage was manifested in each of the impellers by the formation of deep pits (in excess of 1/4-in.), the location of damaged areas varying with impeller geometry. Pit formation appeared to have occurred by uniform rather than preferential removal of metal components. Each of the impellers exhibited heavily carburized zones along exposed surfaces. The cause of carburization may be associated with the type of gas purge utilized for these pumps. (auth)
Date: April 10, 1961
Creator: DeVan, J. H.
Partner: UNT Libraries Government Documents Department
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The Inhalation Toxicity of Indium Sesquioxide in the Rat

Description: Albino rats were exposed to a In/sub 2/O/sub 3/ dust aerosol of mean concentration 64 mg/m) for 3 months. The retention of In in the tissues and the mobilization of In from the lungs and tracheobronchlal lymph nodes were determined. The results indicate chemical toxicity. (D.L.C.)
Date: February 10, 1961
Creator: Leach, L. J.; Scott, J. K.; Armstrong, R. D.; Steadman, L. T. & Maynard, E. A.
Partner: UNT Libraries Government Documents Department
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NON-DESTRUCTIVE TESTING OF STAINLESS-CARBON STEEL WELDS. CORE I, SEED 2. Section 2. Test Results T-641300

Description: Results are presented which lead to the conclusion that all the welds that were radiographed appear to be satisfactory for continued use in the plant except in the 1A reactor coolant loop drain weld. The radiograph of this weld indicates the presence of a 3/8 in. transverse defect. The majority of the welds showed indications of porosity. (J.R.D.)
Date: January 10, 1961
Partner: UNT Libraries Government Documents Department
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Study of Factors Influencing Ductility of Iron-Aluminum Alloys. Monthly Letter Report No. 1, June 1, 1961-November 30, 1961

Description: Studies are being made on the effects of variation of aluminum content, heat treatment, surface preparation, and other metallurgical factors on the room temperature ductility of Al-- Fe alloys. The variation of Fe/sub 3/Al order as a function of temperature for 13.9 Alfenol was redetermined under constant instrumental conditions. The variation of the electrical resistivity of the three alloys under consideration with temperature on slow cooling is illustrated. An anomaly in the disordering process near the Fe/sub 3/Al -- FeAl transformation temperature was manifested in the stoichiometric Fe/sub 3/Al alloy. Above a temperature of 490 deg C there was a rapid decrease in the integrated intensity of the (210) FeAl superlattice reflection. The best ductilities obtained corresponded to heat treatments involving slow cooling to produce a high degree of Fe/sub 3/Al order and subsequent annealing of the ordered material for short periods of time near the Fe/sub 3/Al -- FeAl transformation temperature. (M.C.G.)
Date: July 10, 1961
Creator: Rauscher, G. P., Jr. & Nachman, J. F.
Partner: UNT Libraries Government Documents Department
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Tensile Properties of Pyrolytic Graphite to 5000 F

Description: Tensile properties of pyrolytic graphite were measured parallel to the basal planes from room temperature to 5000 deg F. The gage section of the test specimen was 0.06 by 0.10 in. in cross section and3/4-in. long. The specimens were heated in a helium atmosphere by an external graphite heater and were tested at a strain rate of approx 2 x 10/sup -//sup 4/ in./in./sec. Tensile strengths at room temperatare varied from 6,000 to 19,000 psi with elongations of less thsn 1%. At 3000 deg F the strength and elongation were approximately the same as at room temperature. At 4000 deg F there was a very slight increase in the strength and elongation. At 4500 deg F tensile strengths to 35,000 psi and elongations up to 3%, and at 5000"F tensile strengths of 64,000 psi and elongations greater than 70% were measured. At 4500 deg F and above load-deformation curves were recorded. Microstructure and x-ray diffraction patterns showed that marked structural changes accompsny deformation at 5000 deg F. Large changes in room-temperature dimensions, parallel and perpendicular to the basal planes, were measured after heating, with no load, to temperatures in this same range. (auth)
Date: March 10, 1961
Creator: Kotlensky, W. V. & Martens, H. E.
Partner: UNT Libraries Government Documents Department
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Thermoelectric Nuclear Fuel Element Quarterly Progress Report, April-June 1961

Description: Uranium-bearing thermoelectric compounds are now being prepared by tantalum bomb melting and by the hydride process. Tests of devices made up from these compounds indicate that the main fabrication problems are densification and contact bonding. Data from a hot-swaged pellet and a swaged device of US/sub 2/ indicate some promise for that compound. Improvements in techniques of thermoelectric parameter measurements include programming of automatic test data recording at desired intervals around the clock; increased accuracy and versatility of measurements through use of a newly-constructed adjustable precision resistor; and a method for measuring which should lead to an experimental means for determining the thermoelectric figure of merit, Z. Potential profile studies on PbTe pelleta are yielding important information on contact resistance parameters. A fission-fired thermoelectric generator is being prepared for the next in-pile test. (auth)
Date: July 10, 1961
Partner: UNT Libraries Government Documents Department
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SOME EXPERIENCES IN THE WELD FABRICATION OF REFRACTORY METALS

Description: Discussion is given on the welding fabrication of tungsten, molybdenum, niobium, and tantalum. Properties which make the four refractory metals important are tabulatcd along with titanium which is given for comparison. Extensive evaluation was conducted using the gas, tungsten arc welding process employing both manual and machine welding. Design data were obtained exclusively from machine welded sheet materials. Flash welding, resistance spot welding and brazing, electron beam welding, and high frequency resistance welding processes were also applied to molybdenum alloys. The oxidation of molybdenum, tantalum, and niobium in flowing air at 2000 deg F is also given. (P.C.H.)
Date: February 10, 1961
Creator: Thompson, E.G.
Partner: UNT Libraries Government Documents Department
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HANFORD STUDIES FOR EGCR COMBUSTION CHARACTERISTICS. Summary Report

Description: The temperature, geometry, and flow conditions which exist in the EGCR were duplicated in a mock-up designated as the EGCR Burning Rig to establish the combustion conditions in the reactor. The conditions under which the EGCR Burning Rig will ignite were established and an analytical model was developed which predicts these conditions. Because the Burning Rig cannot exactly dupIicate the reactor situation the final prediction of the safety of the EGCR must rest on computer calculations employing the above analytical model. No advantage in retarding combustion was found in using silicon carbide coated fuel sleeves. The negative results of these tests are due both to the particular geometry of the EGCR moderator and sleeves as well as to the fact that all sleeves tested contained imperfections in the coatings. Chlorine was demonstrated to be an effective agent for extinguishing graphite fires. Concentrations in air of about 1% were observed to extinguish graphite fires at temperatures as high as 1000 deg C. (auth)
Date: October 10, 1961
Creator: de Halas, D.R.; Dahl, R.E. & Jackson, J.L.
Partner: UNT Libraries Government Documents Department
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THE RECOVERY OF FISSION PRODUCT RARE EARTH SULFATES FROM PUREX 1WW

Description: Cerium- and 144 promethium-147, accompanied by rare earths resulting from fission or decay can be removed from Purex 1WW in>90% yield as an insoluble, crystalline sodium-rare earth double sulfate. Precipitation is initiated by a one-to-three hour equilibration at 90 deg C and centrifugation at 90 deg C to take advantage of the lower solubility of the double sulfate salt at a higher temperature. The sulfate concentration should be one molar and the solution pH at the time of precipitation should be 0.5 to 1.5. The addition of tartrate ion to complex the iron allows the use of a higher pH and sulfate concentration, gives a more complete separation from iron, and a quantitative recovery of the rare earths. The double sulfate precipitate can be dissolved in dilute nitric acid or converted to the carbonate and then dissolved to yield a solution for further processing. The double sulfate precipitation of the rare earths, with tartrate added, gives a good separation from impurities. One-cycle decontamination factors of 150 for Zr-Nb and 1100 for Ru-Rh have been achieved in laboratory tests. Tests in the Purex head-end equipment with up to twomegacurie batches of cerium have corroborated the laboratory results. Decontamination factors of 70 for iron, 10 for zirconium, 20 for niobium and 25 for ruthenium have been obtained. It was found wise to limit the batch size because decay heat leads to partial calcination in the centrifuge and to difficulty in redissolution. (auth)
Date: May 10, 1961
Creator: Wheelwright, E.J. & Swift, W.H.
Partner: UNT Libraries Government Documents Department
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A Method of Determining the Intermediate Energy Neutron Dose

Description: The intermediate energy neutron flux existing outside the biological shielding of reactors has not been studied to any great extent previous to this time, because of the lack of an instrument capable of detecting neutrons in the intermediate energy range. The instrument used at the MTR utilizes polyethylene spheres of various sizes to give different amounts of moderation and absorption to the impinging neutrons. A procedure for the approximate determination of the relative number of intermediate energy and fast neutrons is given. By graphical methods the following information is obtained: (1) fraction of intermediate neutrons, (2) fraction of fast neutrons, and (3) the approximate average energy of the fast neutrons. Since the instrument described can be used to determine the thermal neutron flux independent of intermediate and fast fluxes, only one instrument is required to determine the neutron flux in all three energy ranges. Dose calculations indicate the intermediate range neutrons give a dose greater than the dose delivered by fast neutrons around the MTR-ETR reactors under normal operating conditions. (auth)
Date: March 10, 1961
Creator: Hankins, D. E.
Partner: UNT Libraries Government Documents Department
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CHARGING AND DISCHARGING OF DEMINERALIZER RESINS. CORE I, SEED 2. Test Results (T-612085). Section 1

Description: An investigation was conducted to flush the 1BD coolant purification system demineralizer of resin and to measurc the radiation level at pornts on the resin discharge line. It was found that the system demineralizer was satisfactorily flushed of resin. It was also found that the amount removed is measured by the amount required to recharge the demineralizer. (J.R.D.)
Date: January 10, 1961
Partner: UNT Libraries Government Documents Department
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Air Lift Performance at Low Liquid Rates Using Oversized Piping and Lateral Runs

Description: The use of oversized piping in an air lift for transferring solutions at rates less than 5 liters per hour was proven feasible with certain limitations. Reliable operation was also obtained with air lifts containing a lateral run inserted between the point of air injection and the final discharge point. Discharge of the air lifts, especially at low liquid flows, was very erratic under the conditions studied. (auth)
Date: October 10, 1961
Creator: Chamberlain, H. V.
Partner: UNT Libraries Government Documents Department
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CHEMISTRY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING JUNE 20, 1961

Description: Progress in the fields of nuclear chemistry, isolation and chemical properties of synthetic elements, chemical separation of isotopes, radiation chemistry, organic chemistry, chemistry of aquecus systems, electrochemistry of corrosion, nonaqueous systems at high temperature, and chemical physics for the year ending June 20, 1961, is reported. Separate abstracts were prepared for each topic. (M.C.G.)
Date: October 10, 1961
Partner: UNT Libraries Government Documents Department
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CATASTROPHIC OXIDATION OF HIGH-TEMPERATURE ALLOYS

Description: The growth of nonprotective, crust-like oxide films was encountered in high-temperature alloy systems that contain molybdenum, vanadium, or tungsten as strengthening additions. The cause of accelerated oxidation in such alloys appears to be associated with the characteristically low melting temperatures of oxides of these refractory elements. The factors that contribute to a breakdown of oxidation protection in these systems are outlined and remedial methods which may be used to avoid catastrophic oxidation are discussed. Commonly encountered service failures that have resulted from catastrophic oxidation are also described. (auth)
Date: November 10, 1961
Creator: DeVan, J. H.
Partner: UNT Libraries Government Documents Department
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NEUTRON FLUX AND Cd RATIO MEASUREMENTS IN THE HN-1 BEAM HOLE FOR THREE FUEL LOADINGS OF THE OAK RIDGE RESEARCH REACTOR

Description: Neutron flux measurements were made in the Oak Ridge Research Reactor beam hole HN-l shield plug. at low reactor power (N/sub L/) with three fuel configurations. The purpose of these tests was to determine the most favorable fuel arrangement in the region of the experimental hole in order to permit minimization of exposure time of an in-pile slurry loop experiment using pure thoria. It was found that the perturbed thermal neutron flux decreased by factors of 2, each 1.4 in., at the forward end of the beam hole. Maximum and average fluxes observed for three fuel configurations were: high, 9.7 x l0/sup 13/ , 5.6 x 10/sup 13/; intermediate, 8.0 x 10/sup 13/, 4.7 x l0/sup 13/; and present operating, 7.4 x l0/sup 13/, 3.8 x 10/sup 13/. In the high and intermediate configurations fuel elements were located in the outer row of the lattice adjacent to the beam hole. Cadmium ratios were generally high (22 to 111) implying low available epi-cadmium flux under any of these configurations. (auth)
Date: October 10, 1961
Creator: Shor, A.J.f Mauney, T.H.
Partner: UNT Libraries Government Documents Department
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SUMMARY OF HRT RUN 21

Description: The HRT was operated experimentally during run 2l at powers up to 5 Mw to explore the limiting conditions of fuel stability and to demonstrate the reliability of the system. The effect of core pressure on fuel stability was investigated over the range from l250 to 1750 psig. Stable operation at 5 Mw (2.6 Mw in the core) was demonstrated at 1250 psig. At 1600 and 1750 psig, fuel instability accompanied by rapid loss of reactivity occurred at powers down to 2.5 Mw. The threshold power for reactivity loss at intermediate pressures was raised by increasing the fuel acid/sulfate ratio from 0.28 to 0.34. In other studies the fuel temperature was varied from 240 to 275 deg C at sev eral different pressures. In some instances the reactor appeared more stable at the lower temperatures. The effects of suspended solids and oxygen concentration were examined briefly without conclusive results. At times during operation at low pressure and high power, an increase in reactivity, indicating deposition of uranium on the core tank, was observed. During an experiment to investigate this effect, a hole was melted in the core near the equator. The reactor was shut down for examination and modifications to improve the core hydrodynamics. Experiments on internal recombination showed solution recombination- rate constants significantly higher than were previously measured in out-of-pile experiments. Equipment performance was generally satisfactory. A diaphragm failure in one head of the fuel feed pump, minor leakage through four valves, low efficiency of the low-pressure recombiners and rupture of the air-cooled condenser by freezing were the principal difficulties. There was one period of 105 days of continuous operation. During run 21 operations, which extended from October 4, l959, to January 23, l960, the reactor was critical for 2455 hours and produced 5598 Mwh(th). (auth)
Date: October 10, 1961
Creator: Haubenreich, P.N.; Bauman, H.F.; Bradley, N.C.; Engel, J.R.; Kolb, J.O.; Piper, H.B. et al.
Partner: UNT Libraries Government Documents Department
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