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Preparation of Charge Materials for Ornl Electromagnetic Isotope Separators
SEPARATORS. C. W. Sheridan, H. R. Gwinn, and L. O. Descriptions are given of procedures, techniques, and equipment used to prepare charge materials for electromagnetic isotope separators at ORNL. Data on ion outputs during processing, charge consumption rates, and process efficiencies are given for 54 elements. (auth)
Date:
August 1, 1962
Creator:
Sheridan, C W; Gwinn, H R & Love, L O
Object Type:
Report
System:
The UNT Digital Library
Chemical Technology Division, Unit Operations Section Monthly Progress Report, February 1962
In the operation of 6-in.-dia. foam-liquid columns, increase in either the liquid flow or foam flow caused increased channeling with increased HTU. Flooding values for the Immi mixer-settler were obtalned using the amine extraction final cycle Pu flowsheet. Two tests of the addltlon of uranyl nitrate to a thoria sol were made, one of which gave a good product and the other a product which disintegrated during calcination. Material balances for 22 waste calcination runs are summarized. (auth)
Date:
August 23, 1962
Creator:
Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Object Type:
Report
System:
The UNT Digital Library
THE FERRITE BIASING SYSTEM FOR THE RADIO FREQUENCY CAVITIES OF THE PRINCETON-PENNSYLVANIA 3 Bev PROTON SYNCHROTRON
A description is given of the ferrite biasing system for the four tuned radio frequency cavities of the synchrotron. Each ferrite loaded double cavity has a single turn bias winding which is driven to a peak current of 13,500 amperes by a push-pull transformer arrangement. There is automatic tap changing of the transformer to accommodate the variable impedance load (for power considerations). The programming and frequency response of the system have to be such that each cavity can operate as the reso nant circuit of a self tracking radio frequency amplifier over the frequency range 6.5 to 30 Mc at the 20 cps repetition rate of the synchrotron. Between acceleration cycles it is necessary to program the ferrite to a given magnetic state, near that of maximum radio frequency permeability. (auth)
Date:
August 29, 1962
Creator:
Rees, G.H.
Object Type:
Report
System:
The UNT Digital Library
A TRANSISTORIZED ALPHA COUNTER FOR AN ALPHA GAUGE
A transistorized instrument prototype was designed and constructed to replace a vacuum-tube instrument in an alpha gauge, which measures the thickness density of gases. The instrument amplifies, shapes, discriminates, and counts alpha pulses from a Au-Si surface-barrier detector exposed to an alpha source in a gas-filled chamber. The circuit consists of a charge-sensitive preamplifier, a main amplifier with pulse clipping, a Schmitt trigger, a diode pump, and a count rate meter. Preliminary tests gave results comparable to the vacuum-tube instrument. Accuracy of counting was within 10% for 0.5- to 10-Mev alpha particles emitted at a maximum rate of 10/sup 6 per sec. The instrument was stable at 25 to 55 deg C, is small and portable, and costs less than 0. An infinitely thick, alpha source that will give a high count rate is being constructed for final tests. (auth)
Date:
August 23, 1962
Creator:
Kopp, M.C.
Object Type:
Report
System:
The UNT Digital Library
The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah
A detailed 4urvey of the radiation from the N.S. Savannah shield was made. The study was accomplished with the reactor at its full power of 69 Mw during a cruise of 2821 miles. The results of the detailed shield survey show that the design dose rate of 0.5 rem/yr for passenger spaces is not exceeded in any region to which passengers have access. ln the area restricted to crew access the design dose rate of 5.0 rem/yr is nowhere exceeded except in a small region on D'' deck in a room to which entry can readily be controlled. Specifications for cargohold dose rates, 0.5 rem/yr at 1/5 full power, are satisfactorily met. Additional data obtained include measurements of special points for comparison with dose rates predicted in design calculations, and an experiment examining the result of loss of water from the Savannah's subreactor shield tanks. Predicted dose rates were conservatively higher than the dose rates measured, and the result of the water-loss experiment showed that even with a total emptying of the tanks a safe condition exists only a few feet from the shield. (auth)
Date:
August 29, 1962
Creator:
Blizard, E.P.; Blosser, T.V. & Freestone, R.M. Jr.
Object Type:
Report
System:
The UNT Digital Library
EFFECT OF NEUTRON IRRADIATION ON MATERIALS SUBJECTED TO MULTI-AXIAL STRESS DISTRIBUTIONS. Quarterly Report for the Period Ending June 30, 1962
Activities in a program to determine the effects of neutron irradiation on A-302B steel are reported. Plans are discussed concerning performance tests on tensile, notched tensile, tube, and Charpy specimens. An irradiation capsule design was finalized. A theoretical analysis of the critical conditions arising in a tube subjected to both internal pressure and axial load is included. (J.R.D.)
Date:
August 13, 1962
Creator:
Trozera, T A
Object Type:
Report
System:
The UNT Digital Library
SIZE ANALYSIS OF PARTICULATES FOUND IN AIR AT HANFORD PLUTONIUM FABRICATION FACILITIES
A study was made on the characteristics of radioactively contaminated air at Hanford work locations. One of the main objectives in this study is to define the size of particular air contamination in plutonium handling facilities. In addition to characterizing the particulate contamination, it is desirable to know the normal background particle size distribution. Data are summarized on general particle size distribution and radioactive particle distribution at two Hanford plutonium fabrication facilities. (auth)
Date:
August 1, 1962
Creator:
Selby, J.M.
Object Type:
Report
System:
The UNT Digital Library
CALCULATIONS OF THE DOPPLER COEFFICIENT OF LARGE CERAMIC-FUELED FAST REACTORS
ABS>Calculations of the Doppler coefficient of large, ceramicfueled fast reactors containing plutonium were made by means of the ELMOE program to provide accurate flux calculations. The temperature-dependent cross sections of P. Greebler et al., for U/sup 238/ and Pu/sup 239/ were used. Doppler coefficients of the order of 10/sup -5/ ntermediate tem k/ C were obtained, in agreement with Greebler's results. Coefficients of carbide fueled reactors are about 0.7 of those of oxide-fueled reactors at the same fuel enrichment. Effective coarse- group elastic-removal cross sections for light elements are tabulated. It appears that, with tabulations of this sort as a guide, coarse-group sets of cross sections can be constructed to give adequate accuracy in calculations of Doppler coefficients without use of ELMOE. (auth)
Date:
August 1, 1962
Creator:
Bhide, M.G. & Hummel, H.H.
Object Type:
Report
System:
The UNT Digital Library
LOADING AND ELUTION CHARACTERISTICS OF SOME NATURAL AND SYNTHETIC ZEOLITES
The cation exchange characteristics of several commercially available zeolites were evaluated, Equilibrium loading characteristics and exchange capacities were determined experimentally in the binary systems cesium-lithium, cesium-- sodium, cesium--potassium, cesium-Tubidium, cesium -- hydrogen, cesium-- ammonium, strontium-- magnesium, strontium-- calcium, strontium-- barium, and strontium-- hydrogen for several zeolites. Exchangeable cation fractions in the equilibrium solutions were varied from 0.2 to 0.00001, while the total normality of the system constituents was held constant. Results were plotted as equivalent fraction of the traced cation on the zeolite at equilibrium vs. the fraction of traced cation remaining in the equilibrium solution. If an influent composition is known, and falls in the system listed above, zeolite column loading may be read directly in univalent-univalent or divalent-divalent systems. However, in the strontium-sodium or strontium-- hydrogen systems, a k value must be used because squared terms appear in the equilibrium expression as follows: 2 Na- zeolite plus or minus Sr-solution in equilibrium 2 Nasolution + Sr-zeolite, or k = (Sr-zeolite)(Na-solution)/ (Na-zeolite)2(Sr-solution). The k for a given cation is a function of zeolite loading with that cation. Several column 50% loading capacities were determined to randomly test the validity of the above curves to predict column capacities, Several columns …
Date:
August 10, 1962
Creator:
Ames, L.L. Jr. & Knoll, K.C.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Technical Report on Spert Project, January-March 1962
None
Date:
August 10, 1962
Creator:
Schroeder, F.
Object Type:
Report
System:
The UNT Digital Library
Administration of ORNL Research Reactors
Organization of the ORNL Operations division for administration of the Oak Ridge Research Reactor, the Low Intensity Testing Reactor, and the Oak Ridge Graphite Reactor is described. (J.R.D.)
Date:
August 20, 1962
Creator:
Casto, W. R.
Object Type:
Report
System:
The UNT Digital Library
TWO AUXILIARY CODES FOR USE WITH RENUPAK
Two IBM-7090 codes were written to aid the user of the neutron moments method code RENUPAK. One code computes and punches response function input cards for RENUPAK or NIOBE (another neutron transport code). The second code reads RENUPAK flux tapes and prints out a compact edit including dose rate as a function of distance. (auth)
Date:
August 10, 1962
Creator:
Trubey, D.K.
Object Type:
Report
System:
The UNT Digital Library
Reactor Controls Reliability and Maintenance at the ORR
Early evaluation and study of the various criteria for the ORR clearly established the requirements for the fundarnental safety and control instrumentation, and the instrumentation was well integrated into the design and construction of the plant. However, it was not designed for the optimum of maintenance convenience and minimum reactor down time in the event of instrument failure. The revisions and additions that have been made in the physical plant and maintenance which have resulted in a definite reduction of reactor down time resulting from instrument failure in the reactor and in the experiments are described. (auth)
Date:
August 28, 1962
Creator:
West, K.W.
Object Type:
Report
System:
The UNT Digital Library
The Specific Heat of Dysprosium Metal Between 0.4 and 4 K
Submitted to Illinois Inst. of Tech., Chicago. A He/sup 3/ cryostat was built to measure the specific heat of rare earth metals which have a component, at low temperatures, attributable to the electrons in the incomplete 4f shell. The specific heat of dysprosium from 0.4 to 4.2 deg K was measured. Pertinent theories about specific heats are outlined. The apparatus included the cryostat, vacuum and He/sup 3/ systems, calorimeter, carbon thermometer, heater, and magnetic thermometer. The experimental procedure is described and results are presented in graphic and tabular form. The specific heat rose sharply below 1 deg K. An anomalous hump was centered about 2.35 deg K. (M.C.G.)
Date:
August 1, 1962
Creator:
Guenther, R. A.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
Nuclear Safety Program Semiannual Progress Report for Period Ending June 30, 1962
Progress in nuclear safety research and development is reported. Topics covered include: reactivity effects of fuel displacements in a pool-type reactor, release of fission products on out-of-pile melting of reactor fuels, release of fission products on in-pile melting of reactor fuels, fission product transport evaluations, characterization and control of accident-released fission products, nuclear safety pilot plant, preparation of reactor containment hardbook, and radiochemical plant safety studies. (M.C.G.)
Date:
August 24, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
X-Ray Diffraction Study of Cs$sub 3$ZrF$sub 7$
None
Date:
August 1, 1962
Creator:
Robbins, G. D. & Burns, J. H.
Object Type:
Report
System:
The UNT Digital Library
High-Temperature Reactions of Type 304 Stainless Steel in Low Concentrations of Carbon Dioxide and Carbon Monoxide
Compatibility studies of type 304 stainless steel in helium containing low concentrations of CO and CO/sub 2/ were conducted. The oxidation rates were insensitive to impurity concentrations between 0.0006--0.3 vol% in the temperature range 400--1000 deg C when P/sub co2/P/sub co/ was less than 0.66. Ratios above this value resulted initially in a slow oxidation rate, but was followed by an accelerated attack. The incubation period for the break-away varied with the P/sub co2//P/sub co/ ratio and the pressure of the two gases. The oxidation reactions proceeded through a selective depletion of chromium from the alloy which increased the carbon solubility and depletion of nickel which led to the transformation of austenite to ferrite. Parabolic reaction rates were observed for the formation of the protective oxides. Arrhenius plots of rate constants versus 1/T indicated the presence of several oxides which was confirmed by other methods. Carburization or decarburization reactions occurred coincidentally with oxidation and depended upon temperature and (P/sub CO/)/sup 2/ /P/sub CO2/ and the P/sub co2//P /sub CO/. Neither was detected below 600 deg C. Between 600--900 deg C, only carburization occurred and appeared to be mainly dependent on the temperature. Above 900 deg C, both carburization and decarburization …
Date:
August 29, 1962
Creator:
Inouye, H.
Object Type:
Report
System:
The UNT Digital Library
AN EVALUATION OF MATERIALS OF CONSTRUCTION FOR THE SULFLEX AND ZIRFLEX PROCESSES
concentration is not greater than four molar and the nitric acid greater than five molar. In addition, core dissolutions should be done below the boiling point, and heat transfer surface termperatures during core dissolution should be maintained below 240 deg F. Carpenter 20 is probably less satisfactory for Sulfex service because of selective weld attack. Neither Ni-o-nel, 309 SCb, or 304L is a satisfactory construction material for uninhibited Zirflex solutions. Cupric ion lowers the corrosion rate of 309 SCb to 30--40 mils per year, but is not a satisfactory inhibitor for 304L or Ni-o-nel. (auth)
Date:
August 1, 1962
Creator:
Katz, H. & Isler, R.
Object Type:
Report
System:
The UNT Digital Library
Laboratory-Scale Demonstration of the Fused Salt Volatility Process
The feasibility of processing enriched irradiated zirconium--uranium alloy fuel by the fused salt-fluoride volatility procedure has been demonstrated in laboratory tests with fuel having a burnup of over 10%. Uranium recoveries were greater than 99% and decontamination factors for radioactive fission products were 10/sup 6/ to 10/sup 6/. The UF/sub 6/ product contained significant quantities of nonradioactive impurities; additional work in this area is needed. (auth)
Date:
August 1, 1962
Creator:
Cathers, G. I.; Jolley, R. L. & Moncrief, E. C.
Object Type:
Article
System:
The UNT Digital Library
THERMIONIC CONVERTERS FOR COMPACT NUCLEAR POWER PLANTS
A brief review of several thermionic nuclear power plants leads to the conclusion that the in-core concept is the most practical and useful system for space applications. Fundamental considerations indicate that emitter temperatures from 1500 to 1900 deg C are required for this concept, and that the high work function refractory metals are the best electrode materials for achieving the required performance and lifetime at these temperatures. The analytical and experimental technology developed for systematically defining the optimum materials and operatlng conditions is described, along with the significance of the experimental results obtained. These results have shown that the required performance can be obtained with the elementary cesium vapor diode converter. It was also shown that impurities cause pronounced effects on both performance and lifetime, and that their suppression or controlled utilization is an important aspect of the present approach. (auth)
Date:
August 1, 1962
Creator:
Rasor, N.S. & Weeks, C.C.
Object Type:
Report
System:
The UNT Digital Library
Experiment Facilities of the Oak Ridge Graphite Reactor
Up-to-date descriptive material and dimensional sketches of the ORNL Graphite Reactor and its experimental facilities are presented. (P.C.H.)
Date:
August 17, 1962
Creator:
Sheppard, S. D.
Object Type:
Report
System:
The UNT Digital Library
An Out-of-Pile Electron Irradiation Circulating Loop for Fouling Studies
An out-of-pile electron irradiation circulating loop was developed to study the problem of fuel element fouling in organic cooled reactors. Unlike pyrolytic loops and capsules, the irradiation loop operates at temperatures, pressures, fluid dynamics, geometry, and radiation damage which closely resemble reactor conditions. The loop is run in conjunction with the 4-kw -- 6-Mev electron linear accelerator. The thickness of the fouling film deposited in the irradiation cell is measured and the film subjected to chemical analysis. Test results showed that clean coolant did not foul; reactor coolant (Core II) with particulate matter fouled; heaviest film was found in the radiation area; and lower fouling occurred at high velocity. (auth)
Date:
August 1, 1962
Creator:
Mengelkamp, R. A.; Hudson, P. S. & Hillyer, J. C.
Object Type:
Report
System:
The UNT Digital Library
THE OAK RIDGE RESEARCH REACTOR (ORR), THE LOW-INTENSITY TESTING REACTOR (LITR), AND THE OAK RIDGE GRAPHITE REACTOR (OGR) AS EXPERIMENT FACILITIES
>Characteristics of the ORR, LITR, and OGR that experimenters have found to be important are listed. The results of a survey conducted among experimenters on the utility of the reactors for various types of experiments are discussed, and some changes which might be made to improve the utilization are listed. A brief outline, with references, of most of the experiments currently being performed is included. (auth)
Date:
August 28, 1962
Creator:
George, K.D.
Object Type:
Report
System:
The UNT Digital Library
OGRE-P2, a Monte Carlo Program for Computing Gamma-Ray Leakage From Laminated Slabs With a Distributed Source
A Monte Carlo program OGRE-P2 was written for the IBM-7090 to solve the problem of gamma radiation from a slab of laminated regions composed of various materials. The dose rate is calculated on one side of the slab. (J.R,D.)
Date:
August 10, 1962
Creator:
Trubey, D. K.; Penny, S. K. & Emmett, M. B.
Object Type:
Report
System:
The UNT Digital Library