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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


Description: Tables of temperature dependent coefficients are presented for the computation of thermodynamic properties of gaseous UF/sub 6/ using equations which express the properties as expansions in powers of pressure. The various coefficients listed were computed in one degree increments for a temperature range of 500 to 999 deg R. This set of tables was computed by use of a virial equation representation for the equation of state and the thermodynamic properties were derived from this representation. (auth)
Date: September 30, 1960
Creator: Parks, B.H. & Burton, D.W.
Partner: UNT Libraries Government Documents Department


Description: Samples of grade A Monel snd grade A nickel were subjected statically in a single reactor to an undiluted atmosphere of gaseous fluorine at pressures up to one atmosphere absolute and temperatures up to 1500 deg F. The grade A Monel was conservatively estimated to have consumed at least 40 times as much fluorine as grade A nickel during the entire period of the investigation. Samples of fused alpha Al/sub 2/O/sub 3/, alpha -Al/sub 2/O/sub 3/- MgO spinel, and alpha -Al/sub 2/O/sub 3/-NiO--nickel cermet were exposed to undiluted fluorine at one atinosphere absolute pressure at temperatures of 1340 and 1500 deg F. Results indicated that the alpha -Al/sub 2/O/sub 3/ is as good as the Ni in the region of 1300 deg F. Grade A nickel samples coated with nickel fluoride filins of 37,000 and 74,000 A, respectively, were exposed to an absolute pressure of gaseous UF/sub 6/ of 12 cm of Hg at temperatures of 1000 and 1800 deg F. (W.L.H.)
Date: July 28, 1959
Creator: Hale, C.F.; Barber, E.J.; Bernhardt, H.A. & Rapp, K.E.
Partner: UNT Libraries Government Documents Department


Description: Two thermobalances have been constructed which make use of an improved reactor design for the study of gas-solid reactions as they apply to the conversion of uranium oxide materiels to uranium tetrafluoride. Since temperature has been recognized as one of the most important rate-governing factors for both of the reactions involved in this transformation, the reactor design provides for maintaining the sample temperature constant to +- 1.0 deg C. at any selected temperature over the range 100 to 600 deg C. Rate-controlling variables such as reaction temperatures, gas flow rates, preheating time and bed depth have been studied in order to establish the ranges over which small variations in these factors can be ignored. (auth)
Date: September 16, 1964
Creator: Orrick, N. C.; Hale, C. F.; Jones, C. G.; Rapp, K. E. & Barber, E. J.
Partner: UNT Libraries Government Documents Department

Evaluation of variables which affect the hardness of nickel plate deposited from watts-type baths

Description: In the course of the Cascade Improvement Program, many component equipment parts will be electroplated with nickel for corrosion protection. The maximum hardness which will be acceptable in the electroplated deposit is specified in Union Carbide's Job Specification JS-1396, Revision 3, entitled Electroplated Nickel Coatings on Steel Parts. The hardness specification is intended primarily as a control over both organic and inorganic impurities in the deposit. This report covers a study evaluating several of the numerous controllable variables which influence the hardness of the nickel plate deposited from a Watts-type bath. The variables tested were: 1) bath composition, 2) pH, 3) current density, 4) anode-cathode area ratio, and 5) bath temperature. Within the tested ranges of the variables studied, the pH and current density had the most influence on the plate hardness. The softest deposit was obtained with a bath pH of 1.5, a current density of 30 to 40 amperes/square foot, and with the anode-cathode area ratio in the range of 3:1 to 1:1. (auth)
Date: January 21, 1976
Creator: Petit, G. S.; Wright, R. R. & Neff, W. A.
Partner: UNT Libraries Government Documents Department

High Temperature Corrosion of Some Metals and Ceramics in Fluorinating Atmospheres

Description: Abstract: The results of this investigation leave little doubt that diffusion of the fluorinating gas along the grain boundaries of the nickel fluoride film to react at the metal-scale interface is the primary mechanism of attack upon pure nickel and its more promising alloys.
Date: September 30, 1960
Creator: Hale, C. F.; Barber, E. J.; Bernhardt, H. A. & Rapp, Karl E.
Partner: UNT Libraries Government Documents Department

Uniformly Reactive Uranium Dioxide from a Single Oxidation-Reduction Cycle

Description: Abstract: By use of a modified thermobalance and reactor as the primary experimental tool for sample preparation and evaluation, a process has been developed by which parent uranium feed materials of a widely variable reactivity and composition may be converted to a uniformly reactive uranium dioxide.
Date: August 28, 1963
Creator: Orrick, N. C.; Jones, C. G.; Hale, C. F.; Barber, E. J. & Rapp, Karl E.
Partner: UNT Libraries Government Documents Department

Criticality-Accident Dosimetry Studies

Description: Experiments were carried out to (1) explore possibilities for developing a less expensive device than the Hurst threshold detector unit (TDU) for monitoring possible accidental critical reactions in uranium-processing facilities, (2) to study the precision and accuracy of the TDU, and (3) to evaluate the ORNL film badge in mixed neutron-gama radiation fields.
Date: October 15, 1964
Creator: Bailey, J. C.
Partner: UNT Libraries Government Documents Department

Evaluation of a 4$pi$ neutron counter for the nondestructive analysis of uranium-234 in uranium hexafluoride

Description: A neutron counter has been evaluated for the nondestructive analysis of $sup 234$U in uranium hexafluoride. The instrument was designed by Los Alamos Scientific Laboratory for the Nuclear Safeguards Program. The method assumes that the only source of neutrons is from $sup 19$F($alpha$, n)$sup 22$Na reaction from $sup 238$U, $sup 235$U, and $sup 234$U, the yield from $sup 234$U being the most abundant. This evaluation shows that the mean of the difference between the 4 $pi$ neutron counting method and mass spectrometry is 0.0002 wt percent uranium- 234 +- 0.00015 at the 95 percent confidence level. However, the presence of $sup 232$U produces significant errors in the system. If the neutron technique is to be used for samples containing $sup 232$U in equilibrium with its daughters, the 2.61-MeV gamma peak of $sup 208$Tl must be measured and used to correct for the $sup 232$U. It has been postulated that the neutron counter might also be used to relate the $sup 234$U content of a sample to the $sup 235$U, thus estimating the $sup 235$U concentration. This evaluation notes, however, that in a variety of uranium feeds and enriched product, the $sup 234$U/$sup 235$U ratio varies too widely to enable a valid $sup 235$U determination.
Date: February 1, 1976
Creator: Mullins, W. T.
Partner: UNT Libraries Government Documents Department

Development of the Continuous Method for the Reduction of Uranium Hexafluoride With Hydrogen-Process Development. Hot Wall Reactor

Description: >A continuous process for the reduction of uranium hexafluoride to uranium tetrafluoride was developed and proved on a pilot-plant scale. Complete conversion to uranium tetrafluoride was realized by contacting gaseous uranium hexafluoride with hydrogen in a heated, vertical, open-tube reactor. The purity and density of the solid product met metal grade uranium tetrafluoride specifications. Some difficulty with the accumulation of fused uranium fluorides in the tower was encountered, however, and it was necessary to stop and desing the unit about every 8 to 24 hours. The reaction of uranium hexafluoride with gaseous trichloroethylene was stadied before the tests with hydrogen were made. Although the reduction to uranium tetrafluoride was complete, the solid product was highly contaminated with the organic by-products of the reaction and was quite low in density. Tests of this method were discontinued when promising results were obtained with hydrogen as the reductant. (auth)
Date: June 27, 1958
Creator: Smiley, S. H. & Brater, D. C.
Partner: UNT Libraries Government Documents Department

Diffusion of Radioactive Gases Through Power Reactor Graphite

Description: Results of a study concerned with the problem of retarding the diffusion of fission products through unclad graphite fuel elements are presented. The pertinent parameters are pointed out, and their relations with the properties of graphite and gas coolants are considered. The effects of parameter variation on the concentration in the reactor primary system and the fission-product diffusion rate into the primary system are also examined. (J.R.D.)
Date: April 1, 1959
Creator: Weissberg, H. L. & Berman, A. S.
Partner: UNT Libraries Government Documents Department


Description: The application of an electronic data processing system to the unique combination of scientific and commercial data processing requirements of nuclear materials management is discussed. The organization and ilow of data from the plant through the data processing equipment to the final report are discussed. Included are topics concerned with the impact of conversion to electronic data processing on personnel, materials management costs, and on other plant organizations. Portions are devoted to programming systems and decision-making abilities of data processing equipment which make these systems readily adaptable to nuclear materials management. (auth)
Date: October 31, 1963
Creator: Hudson, J F
Partner: UNT Libraries Government Documents Department