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32,877 Matching Results
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Observed performance of the Fuel Sample Cooler
Measurements of flow rate through the fuel high-pressure system sampler indicate that the average flow rates is about 0.29 gpm (145 lb/hr) plus or minus 50%, which affords an adequate purge of from 12 to 36 volumes through the sample line if the full fifteen minutes of purging is allowed before isolating the sample. The fuel sample cooler was fund to have adequate capacity to reduce the temperature of the fuel solution form about 275 to 70 C, using pre-heated cooling water at 70 C. Uncertainties in temperature measurements make it impossible to estimate an observed over-all heat transfer coefficient.
Date:
June 3, 1957
Creator:
Van Winkle, R. & Wiethaup, R. R.
Object Type:
Report
System:
The UNT Digital Library
Observed Net Heat Loss from the HRT High-Pressure System
An estimate has been obtained of the heat that should be generated in the HRT core in order to hold the system at operating temperature under no-load conditions. This estimate was made by measuring the feed-water rate to the package boiler during an oxygenated water rung. Results are summarized.
Date:
June 4, 1957
Creator:
Van Winkle, R. & Wiethaup, R. R.
Object Type:
Report
System:
The UNT Digital Library
The Disposal of Power Reactor Waste Into Deep Wells
For various reasons it is not possible to leave the uranium or other nuclear fuel in a power reactor until all of it has been "burned up" by fission. In the case of liquid fuel (homogeneous) reactors a small part is continuously bled out, purified and returned. In the case of solid fuel reactors, fuel elements are periodically removed, reprocessed and the "unburned" fuel put back into service. In both cases the purification produces wastes which contain radioactive fission products and transuranic elements, and it is with the disposal of these wastes that we are concerned. For technical reasons, we will limit our consideration to the wastes from the processing of solid fuel elements, and from the processing of the very similar solid "blanket" elements in which fissionable fuel is made from non-fissionable isotopes of uranium and thorium by interaction with neutrons in the outer regions of the nuclear reactor.
Date:
June 13, 1957
Creator:
De Laguna, Wallace, 1910- & Blomeke, J. O.
Object Type:
Report
System:
The UNT Digital Library
HRT Letdown Valves
To supply information about the several letdown valves which have been in HRT service, a typical valve plug examined by the Metallurgy Section confirms the belief that chemical attack on the Stellite #6 was occurring. It appears that most of the corrosion was due to rinse solutions, since this phenomenon has not been noted on letdown valves in the HRT Mockup where over 90% of the operating time has been with UO2SO4 solutions.
Date:
June 5, 1957
Creator:
Billings, A. M.
Object Type:
Report
System:
The UNT Digital Library
September, 1956, Measure of Radiation level of HRE Fuel System Components (After Storage for 27 Months)
Radiation level measurements of various HRE fuel system components, made in September, 1956, after 27 moths of storage, are compared with the June, 1954, readings before storage. Measurements were made with a standard cutie pie and results tabulated.
Date:
June 5, 1957
Creator:
Haynes, T. E. & Van Winkle, R.
Object Type:
Report
System:
The UNT Digital Library
Chemical Cleaning and Storage of the HRT Steam and Closed Cooling Water Systems
A 10% phosphoric acid solution contain 0.2% "Rodine 45" inhibitor is recommended to be used for the chemical cleaning of the HRT seam and closed colling water systems. Wet storage is recommended for both of these systems. The steam system is to be stored with steam condensate containing 100 ppm hydrazine, and closed cooling water system is to be stored with steam condensate containing 1000 ppm potassium chromate.
Date:
June 5, 1957
Creator:
McLain, Howard A.
Object Type:
Report
System:
The UNT Digital Library
The Reaction of Zirconium with Uranium Dioxide
An investigation of the causes of observed explosive reaction of zirconium-coated uranium dioxide on dissolution in nitric acid was conducted. It was concluded that such a reaction is to be expected. Possible but unconfirmed methods of alleviating the problem are suggested.
Date:
June 11, 1957
Creator:
Robinson, M. T.
Object Type:
Report
System:
The UNT Digital Library
HRP In-Pile Corrosion Test Loops -- Operation of In-Pile Loop L-2-10
Loop L-2-10 was the eighth completed in-pile loop experiment and the first in the HB-2 beam hole at the LITR. The loop was inserted on July 2, 1956 and removed on September 3, 1956. The installation, operation, removal, and general performance of the HRP in-pile solution corrosion loop in the HB-2 beam hole at the LITR are described.
Date:
June 13, 1957
Creator:
Walter, F. J.
Object Type:
Report
System:
The UNT Digital Library
Fuel Exposures in Heterogeneous Thorium Breeder Reactors
This technical report summarizes some preliminary calculations of fuel exposures attainable in heterogeneous reactors, fueled with a mixture of thorium and U233, moderated with D2O and operated with no net loss in fissionable fuel.
Date:
June 13, 1957
Creator:
Prince, B. E. & Jaye, S.
Object Type:
Report
System:
The UNT Digital Library
Summary of Corrosion Data for HRT Mockup Operational Period Ending February 16, 1957
The HRT mockup was shut down February 16, 1957 after operating for 576 hours on high concentration uranyl sulfate. At this time, all corrosion samples in the system were removed and replaced, and the wire extending thought the letdown hear exchanger was removed of examination.
Date:
June 17, 1957
Creator:
Wacker, R. E. & Griese, J. C.
Object Type:
Report
System:
The UNT Digital Library
Liquid-Liquid Extraction of Uranium and Plutonium from Hydrochloric Acid Solution with TRI (Iso-Octyl) Amine. Separation of Uranium and Plutonium from Thorium and Fission Products
A new and rapid method for the liquid-liquid extraction of uranium and plutonium from hydrochloric acid solution is based on the use of tri(iso-octyl)amine dissolved in xylene or methylisobutylketone. Uranium and/or plutonium are separated from thorium, alkalis, alkaline earths, rare earths, zirconium, niobium, ruthenium and other elements which do not form anionic species under the conditions described. The technique may be used for either tracer or macro quantities of uranium. Several practical applications of the method for the separations chemist are proposed.
Date:
June 18, 1957
Creator:
Moore, Fletcher L.
Object Type:
Report
System:
The UNT Digital Library
Spectrophotometric Determination of Cerium with Tiron
A spectrophotometric method for the determination of cerium with Tiron (disodium-1,2-dihydroxybenzene-3,5disulfonate) was applied to the determination of cerium in samples which contain uranium and zirconium. The cerium-Tiron complex in solutions of pH 8 or greater exhibits an absorption maximum of 500 mu . This reagent does not react with any other lanthanide element. The interference of iron, uranium, and zirconium was eliminated by extracting these interfering elements with a solution of trioctylphosphine oxide in cyclohexane. (auth)
Date:
June 14, 1957
Creator:
McDowell, B. L.; Meyer, A. S., Jr. & White, J. C.
Object Type:
Report
System:
The UNT Digital Library
Test Results on a Heater-Cooler Unit for the ORR In-Pile Loop
Tests have been completed on a combination heater-cooler unit for use in in-pile loops designed to operate in beam hole HN-1 of the ORR facility. The unit is designed to use air-water mixtures as the coolant. the coolant flows through a spiral of 3/8-inc. diameter tubing cast in aluminum around the 3/8-in. IPS loop pipe. four 1000-w calrod-type electric heating elements are cast into the aluminum, along with the cooling coils to provide loop heating.
Date:
June 28, 1957
Creator:
Mauney, T. H. & Savage, H. C.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Loop Components and Admixed Thorium-3% Uranium Oxide Slurry in 200A Loop (Summary of Run 200A-10)
A slurry addition system, a venturi in the circulation loop, and two types of sampling systems were tested with 500 and 800 g Th/kg H2O slurries in the 200 gpm loop at 250 C and 1000 psig. The addition system worked satisfactorily while the venturi gave erratic readings during part of the run. Both the capillary and in-line sampling systems proved satisfactory with the capillary sampler being much easier and more convenient to operate. The addition of uranium to the slurry had no appreciable effect on the handling characteristics, the attack rate on 347 SS, the particle size and crystallite size of the thorium oxide. The attack rate was found to be 1 mpy during the first 100 hours of circulation and decreased to 0.4 mpy at the end of the run.
Date:
June 13, 1957
Creator:
Gallaher, R. B.; Kitzes, A. S. & VandenBulck, C. F.
Object Type:
Report
System:
The UNT Digital Library
Thermal Cycling Test of 3 1/2-in. and 4-in. Freeze Flanges
A total of 104 thermal cycles between 250°F and 1350°F were imposed on a 3 1/2-in. and a 4-in. freeze flange to determine their susceptibility to thermal fatigue. The flange clamping arrangement was modified and various gaskets were used during the cycling in an effort to reduce the gas leakage problem.
Date:
February 2, 1961
Creator:
Moyers, J. C.
Object Type:
Report
System:
The UNT Digital Library
Apparent Observations Ionic Sound Waves in an Arc Plasma
Oscillations have been observed in a magnetically supported cylindrical rod of plasma. This rod of plasma can be the discharge occurring in the defining aperture of a Mode II, pressure gradient arc. Similar oscillations can also occur in the column of a Mode I arc. These oscillations appear to be the mechanism that drives the Mode II blowup phenomena.
Date:
February 13, 1961
Creator:
Alexeff, I. & Neidigh, R. V.
Object Type:
Report
System:
The UNT Digital Library
Interim Report - Status of Small Pipe and Tube Disconnects for MSRE Auxiliary Lines
To date, three types of metal-to-metal seal disconnects have been subjected to thermal cycling and make-break tests. In addition, a commercial disconnect has been procured for testing.
Date:
February 21, 1961
Creator:
Holz, P. P.
Object Type:
Report
System:
The UNT Digital Library
HFIR Beryllium Reflector Preliminary Design Report
This report considers the HFIR reflector design criteria and presents a summary of the reflector design. The reflector type chosen as complying best with the established criteria consists of a 3 in. thick removable beryllium annulus utilizing four concentric cylinders with cooling water flowing through the annuli between cylinders, and an outer 9 in. thick permanent beryllium annulus with axial circular coolant holes. Reflector support structures and experimental facilities are described and probable beryllium replacement costs are indicated.
Date:
February 21, 1961
Creator:
Hilvety, Neil
Object Type:
Report
System:
The UNT Digital Library
Determination of the Six Turbulent Reynolds' Stresses by the Hot Wire Method for Arbitrary Intensity and Geometry with Special Application to Axisymmetric Flow
A relationship is derived the mean square fluctuating current of a hot wire anemometer and the sic turbulent Reynolds stresses in the stream-coordinate system without employing the usual low turbulent intensity approximation. The relatively simple result is a consequence of assuming proportionality between the wire current reading and the perpendicular velocity component instead of the non-linear dependence required by King's law. The assumption is valid for instruments equipped with the proper linearizing circuitry. The stream-coordinate Reynolds' stresses are then related to the cylindrical polar Reynolds stresses.
Date:
February 21, 1961
Creator:
Wichner, R. P. & Peebles, F. N.
Object Type:
Report
System:
The UNT Digital Library
HRT Corrosion Samples -- Additional Data on Specimens Removed Prior to Run No. 20.
Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined included (1) core screen samples, (2) core specimen array No. 1, (3) blanket specimen array No. 2, (4) core solution line specimen arrays No. 103 and 103A, (5) blanket solution line specimen array No. 203. Complete information is still not available on all the specimens removed from the reactor, however, those data which have been accumulated are presented. These include corrosion rates, computed from specimen weight-changes, and results of chemical analyses of scales removed from the specimens or specimen holders. Also included in the report is a summary of the HRT operating schedule during exposure of the specimen and of the status of examinations for those specimens removed from the reactor prior to run 20.
Date:
February 2, 1961
Creator:
Baker, J. E.; Silverman, M. D.; Jenks, G. H. & Olsen, A. R.
Object Type:
Report
System:
The UNT Digital Library
Preprocessing of Procedure in the ORACLE-Algol Translator
This report describes the preprocessing stage to be added to the present ORACLE-Algol translator which will enable it to translate programs containing procedures. The Algol 60 procedure is an extremely flexible tool, and its full implementation presents a number of difficulties. Since it is undesirable to undertake major revisions of the existing parts of the translator and impossible to solve all of these difficulties in a processing stage, it was necessary to impose certain restrictions on the use of procedures. The result, however, retains the more basic features of the Algol 60 procedure concept. Most of the algorithms published in the Communications of the Association for Computing Machinery can be handled by the preprocessor with few minor or no changes.
Date:
May 15, 1961
Creator:
Bumgarner, L. L.
Object Type:
Report
System:
The UNT Digital Library
Dynamic Corrosion Screening Tests on Inconel and Nickel in NaCl-MgCl2-UCl3 Bath
Nickel is more susceptible to mass transfer in a 100hr non-isothermal dynamic corrosion system than is Inconel when exposed to a NaCl-MgCl2-UCl3 (50.0-33.3-16.0 mole %) bath at a hot zone temperature 1800 F. No nickel mass transfer was observed in a 500-hr test at 1350 F, but Inconel showed some attack under these conditions. Inconel mass transfer was observed in both tests, being more severe at the higher temperature. On the bases of these preliminary tests, it appears that nickel is a more satisfactory container than Inconel for the chloride bath at temperatures in the region of 1350 F. The chromium is more susceptible to selective leaching from Inconel at 1800 F during a short 100-hr test (0.26% Cr in bath) than in a 500-hr test (<0.001% Cr in bath) at a lower temperature (1350 F ).
Date:
June 19, 1957
Creator:
Jansen, D. H.
Object Type:
Report
System:
The UNT Digital Library
Trip to Selas Corporation of America
On May 23, 1957, a visit was made by the writer to the Selas Corporation of American in Dresher, Pennsylvania. The purpose of the visit was to discuss further investigations into methods of tubesheet brazing by direct heating. Original work along these lines has been carried out at ORNL and is covered by a memo (CF-57-4-57) to W.D. Manly, dated April 16, 1957, and entitled : Investigation of Tubesheet Brazing by a Method of Direct Heating.
Date:
June 18, 1957
Creator:
Franco-Ferreira, E. A.
Object Type:
Report
System:
The UNT Digital Library
Fused Salt Compositions
The compositions of the compounds and fused salt mixtures referred to in the ANP project by numbers are given.
Date:
June 20, 1957
Creator:
Barton, C. J.
Object Type:
Report
System:
The UNT Digital Library