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Preliminary Results of High-Temperature Bare U$sup 235$-C Critical Assembly Measurements
The influence of temperature on the critical buckling or bare graphite assemblies with various carbon-to-uranium235 molar ratios has been measured. A range from l185: 1 to 2l,690: 1 was covered, for 45 to 1205'F. Preliminary results indicate that the fractional rate of change of critical buckling with core temperature varies monotonically with C/U2as ratio by a factor of five over the factor-of-eighteen range in gross C/U2as ratio. This quantity appears to approach asymptotically a value near 2%/l00"F at very high C/U2ss ratios. (auth)
Date:
June 1, 1961
Creator:
Finke, R. G.
Object Type:
Report
System:
The UNT Digital Library
Metal Hydrides for Shielding Applications
Tests were conducted to determine the behavior of lithium hydride and calcium hydride under a variety of conditions. Metals of interest as container materials were subjected to stress-rupture and tensile tests after undergoing one or more thermal cycles to certain maximum temperatures while in contact with lithium hydride at various lengths of time. Calcium hydride was produced and fabricated, then tested to determine some of its physical properties. (auth)
Date:
October 1, 1961
Creator:
Hamill, C. W.; Waldrop, F. B. & Kite, H. T.
Object Type:
Report
System:
The UNT Digital Library
Air Pulser for H-1 Column
Studies the prototype and production air pulse units.
Date:
March 1, 1961
Creator:
Bruns, L.E.
Object Type:
Report
System:
The UNT Digital Library
Force Multiplier for Use With Master Slaves
A force multiplier was designed. This piece of equipment was made to increase the gripping force presently available in the Model 8 master slave. The force multiplier described incorporates a clamp which can be quickly attached to and detached from the master slave hand. (auth)
Date:
June 1, 1961
Creator:
Miles, L. E.; Parsons, T. C. & Howe, P. W.
Object Type:
Report
System:
The UNT Digital Library
Supporting Analysis and Derivation of Dimensional Tolerance Specifications for Core II of SM-1A & PM-2A
A method is presented for translating inspection measurements of fuel plate spacing to obtain minimum coolant channel clearances under reactor operating conditions. Considerations of fuel plate ripple growth and the inspection procedure used are included. The method is applied to establish dimensional tolerance specifications used for the procurement of SM-1A and PM-2A Core II. (auth)
Date:
November 1, 1961
Creator:
Brondel, J. O.
Object Type:
Report
System:
The UNT Digital Library
A Mechanism Explaining the Instability of EBR-I, Mark III
Presented at the International Atomic Energy Agencysponsored Seminar on the Physics of Fast and Intermediate Reactors. Vienna, August 3-11, 196l. A feedback model, was developed to account for resonant instabilities in the Mark II core. In this model, the prompt positive power coefficient effect is ascribed to fuel rod bowing and the delayed negative power coefficient effect to thermally lnduced motions in the lower shield plate. Since this model is supported by observations, it is concluded that the instability of Mark II is chiefly due to lack of radial coupling between fuel rods. (D.L.C.)
Date:
September 1, 1961
Creator:
Smith, R. R.; Matlock, R. G.; McGinnis, F. D.; Novick, M. & Thalgott, F. W.
Object Type:
Report
System:
The UNT Digital Library
HOMOGENEOUS REACTOR PROGRAM PROGRESS REPORT FOR PERIOD FROM DECEMBER 1, 1960 TO MAY 31, 1961
Homogoenous Reactor Test. Four HRT runs were performed to study the reactor behavior with downward core flow. The upper patch was found to have fallen out, resulting in an increase in core-to-blanket mixing. The reactor will not be operated again. In the HRT processing plant, the development of a process for removing Ni and other soluble contaminants from fuel solutions by peroxide precipitation was continued, and efficiency tests of stackfllter iodine traps were performed. Power-trace data and computer analysis of a HRT flow model indicate that the HRT power fluctuations were caused by flow perturbations. A flow diffuser was developed to reduce core wall temperature and core power oscillations. Temperature transients due tc density changes were determined. Engineering Developent. ThO/sub 2/ slurries were found to show a slip effect in small-bore capillary tubes, while chemically dispersed slurries showed no such effect. Slurry friction factors in turbulent flow were correlated with Reynolds numbers. Solution Fuels. The stability of Pa tracers in Th(NO/sub 3/)/sup 4/ HNO/sub 3/ solutions was studied at 21 to)200 deg C. The effect of inorganic ions on the solubility of H/sub 2/ in H/sub 2/O is shown graphically. The solubility and nature of UO/sub 3/ hydrates in H/sub …
Date:
September 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
POSTIRRADIATION EXAMINATION OF 17-4 PH STAINLESS STEEL CONTROL ROD DRIVE RACK FROM SM-1 REACTOR
A portion of the control rod drive system in the SM-1 Reactor, fabricated from l7-4 PH stainless steel, was examined at the Oak Ridge National Laboratory (ORNL) hot cells after successful operation in a pressurized-water environment for approximately three years. Examination included visual inspection, magnetic-particle tests, fluorescent penetrant tests, and metallography. No evidence of stress-corrosion cracking or other damage was noted. (auth)
Date:
December 1, 1961
Creator:
Klindt, K.K.; Richt, A.E. & Thurber, W.C.
Object Type:
Report
System:
The UNT Digital Library
Chemistry of Anhydrous Systems Containing Hydrogen Fluoride and Nitrogen Oxides
Nitrosyl and fluoride ions are formed in liquid anhydrous hydrogen fluoride when nitric oxide, nitrogen sesquioxide, nitrogen tetroxide, or nitrosyl fluoride, are dissolved. Vapor infrared analysis was used to study the solution composition and gaseous reaction products. These solutions react with metallic uranium, plutonium, zirconium, iron, and aluminum, as well as ceramic uranium oxide and uranium carbide, forming soluble nitrosyl metal fluoride complexes and liberating nitric oxide. The uranium compound identified as nitrosylium hexafluorouranate, NOUF/sub 6/, was made volatile by passing nitrosyl fluoride gas over the dry salt at 500 deg C. (auth)
Date:
January 1, 1961
Creator:
Horn, Frederick L.; Bartlett, Charles B. & Tivers, Richard J.
Object Type:
Report
System:
The UNT Digital Library
Irradiation of Metal-Fiber-Reinforced Thoria-Urania. Final Report- Metallurgy Program 6.2.4
Randomly oriented fibers of either molybdenum or niobium were incorporated into hot-pressed pellets of 10, 30, and 50 wt% UO/sub 2/ in ThO/sub 2/ to improve thermal conductivity and thermal shock resistance. Pellets, 9.5 mm in diameter and 9.5 mm in length, were irradiated in NaK capsules, both bare and jacketed with Zircaloy-2, with the annulus between pellet and jacket filled with lead or helium. They were irradiated to burnups ranging up to 34 500 Mwd/T (1 0 x 10/sup 21/ fiss/cc) at central temperatures of the order of 3000 deg C. Integral kd theta values ranged from 34 to 129 w/cm. Fracture and metallographic sections of the irradiated specimens confirmed out-of-pile measurements that the molybdenum fibers increased the effective thermal conductivlty of the mixed oxides. It was possible to give the fibered pellets higher heat ratings than unfibered pellets before comparable thermal effects occurred. The fibers tended to reduce central void formation, retard recrystallization, and maintain the integrlty of the pellet. In some helium- bonded specimens, the molybdenum fibers coalesced into a central sphere after melting during irradiation. The coalescence did not occur in lead-bonded specimens. The niobium fibers were found to react with the oxide. Fission gas release …
Date:
December 1, 1961
Creator:
Neimark, L. A.; Kittel, J. H. & Hoenig, C. L.
Object Type:
Report
System:
The UNT Digital Library
The Recovery and Purification of Multi-Kilocurie Quantities of Fission Product Strontium by Cation Exchange
In seven production runs, 75,000 curies of Sr/sup 90/ were isolated and purified in the ion-exchange equipment of Hanford Laboratories High Level Cells. The production goal (60,000 curies of purified Sr/sup 90/) and the time schedule were met or exceeded and the product exceeded the customer's purity requirements. The hot-cell-purified strontium made possible the completion on time of the Weather Bureau power source and the Martin 10 watt SNAP VII-A and VIl-C units. The isotopic purity of the strontium product was 56% Sr/sup 90/. The chemical purity was greater than 95% strontium. The Zr-Nb/sup 95/ contamination of the product was less than 5 x 10/sup -5/ curies per curie of Sr/sup 90/, and the Ce- Pr contamination was less than 1 x 10/sup -5/ curies per curie of Sr/sup 90/. The final run yielded 16,500 curies of Sr/sup 90/ in an eight liter product solution. The product was >98% strontium and contained less than one curie of Zr- Nb/sup 90/ or Ce-Pr/sup 144/. Eleven days of continuous operation were required to complete the run. (auth)
Date:
September 1, 1961
Creator:
Bray, L. A.; Lust, L. F.; Moore, R. L.; Roberts, F. P.; Smith, F. M.; Van Tuyl, H. H. et al.
Object Type:
Report
System:
The UNT Digital Library
Synthesis of Wave-Forming Networks
Passive networks whose specified wave forms are given as a function of time are discussed. The wave forms may be periodic or a single pulse. Suggestions and techniques are presented which should enable a circuit designer with a basic knowledge of network synthesis procedures to obtain wave-forming networks for a wide variety of cases. (auth)
Date:
August 1, 1961
Creator:
LaPatra, J. W.
Object Type:
Report
System:
The UNT Digital Library
THE CONTINUOUS MONITORING OF BORIC ACID CONCENTRATION BY NEUTRON ABSORPTIOMETRY
A neutron absorption cell was built to monttor continuously the boric actd concentration of reactor water flowing through a purtfication loop. The instrument was calibrated over the range from 0 to 2.65 g/l with a maxtmum absolute error of 0.05 g/-l. (auth)
Date:
October 1, 1961
Creator:
Armani, R.J.
Object Type:
Report
System:
The UNT Digital Library
RADIOISOTOPE TECHNIQUES FOR CHEMICAL, PHYSICAL, AND INDUSTRIAL APPLICATIONS
A laboratory manual is given consisting of 14 experiments designed to teach some of the basic fundamentals of the application of radioisotopes, and to introduce the principles of radioisotope technology. The majority of the experiments, while designed to be practical, are planned for scientists having little background in radiochemical and radioisotopc technology, and the remainder are outlined for more advanced personnel. The experiments include isotope production, sample preparation and half life determination, radioactive decay mixture of independent decaying activities, preparation of carrier-free solutions, solubility measurements, tracer techniques by exchange kinetics, diffusion studies, determination of deposit thickness, blending efficiency, beta and liquid level gaging, special handling of radioisotopes in hot cell operations, autoradiography, engine wear studies, and decontami tion of radioactive spillage. (B.O.G.)
Date:
September 1, 1961
Creator:
Cassell, A.J.
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF PLUTONIUM BEARING FUEL MATERIALS. Monthly Progress Letter for Month of August 1961
Surface area measurements on UO/sub 2/-PuO/sub 2/ and PuO/sub 2/ powders are reported. Fabrication and evaluation of PuO/sub 2/ shapes are reported. Work on resonance integrals of UO/sub 2/ and U rods is described. (D.L.C.)
Date:
September 1, 1961
Creator:
Puechl, K.H.
Object Type:
Report
System:
The UNT Digital Library
Pressure Drop of Multirod Elements With Helical Spring Spacers
The pressure drop of a new fuel element design concept of spacing rods by means of helical wire springs was investigated experimentally and analytically. Extensive single- and two-phase pressure drop data at 1,000 psia were obtained for one flow geometry and helical spring spacer. Test conditions ranged from 0.7 to 1.2 x 10/sup 6/ lb/hr ft/sup 2/ in mass velocity and from 0 to 15% in quality. The effect of the specific spring which was tested was to increase the over-all pressure drop by 70%. A general analytical model was developed to predict the pressure drop of an element with helical spring spacers when the pressure drop without springs is known. The accuracy of the model, compared to the experimental data, was better than plus or minus 22%. The analytical model allows determination and evaluation of an optimum helical spring spacer design, so that pressure drop will not be a serious disadvantage. (auth)
Date:
June 1, 1961
Creator:
Quinn, E. P.
Object Type:
Report
System:
The UNT Digital Library
Examination of Uranium From the First Core of the EBR-I. Final Report- Program 6.1.10
The changes due to neutron irradiation which occurred in the highly enriched uranium fuel slugs of the first core of the EBR-I were related to burnup (0 to 0.3 at.%) and to temperature (285 to 395 deg C). Initially, the slugs increased in length with increase in burnup, but at higher burnups the direction of growth reversed itself, and the slugs tended to shrink to less than their original lengths. Temperature became an important factor at the higher levels of burnup in that the ratio of length change to burnup decreased with increasing temperatare. Diameter changes were the inverse of the changes in length. Density decreased almost linearly with burnup and was not affected by temperatare. Hardness increased with increasing burnup but the rate of increase decreased both with increasing burnup and temperature. (auth)
Date:
September 1, 1961
Creator:
Murphy, W. F.; Klank, A. C. & Paine, S. H.
Object Type:
Report
System:
The UNT Digital Library
Data for Elementary-Particle Physics
Elementary-particle data and other reference information for use in high- energy physics are presented in tables and graphs. (M.C.G.)
Date:
October 1, 1961
Creator:
Barkas, W. H. & Rosenfeld, A. H.
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF CENTRIFUGAL COMPRESSORS
Coolant flow for gas-cooled in-pile loops must be supplied during irradiation test runs. A centrifugal compressor has been designed and developed for circulating helium at volume flows from 75 to 250 acfm at compressor suction conditions of 400 psi and 600 deg F. The compressor using grease-lubricated ball bearings has operated satnksfactorily for a total of 3500 hr. (auth)
Date:
October 1, 1961
Creator:
Namba, I.K.
Object Type:
Report
System:
The UNT Digital Library
THEORETICAL STUDY OF OPTICAL PROPERTIES. APPENDIX B: MONOCHROMATIC ABSORPTION COEFFICIENTS FOR NITROGEN, ALUMINUM, AND SILICON. Final Report
None
Date:
September 1, 1961
Creator:
Stewart, J C & Pyatt, Jr, K D
Object Type:
Report
System:
The UNT Digital Library
PHYSICAL PROPERTIES OF URANIUM PROCESS SOLUTIONS
Integral diffusion coefficients, viscosities, densities, and surface tensions were measured for the aqueous uranyl nitrate --nitric acid--aluminum nitrate system. The variation of the uranium diffusion coefficient was determined as as a function of uranium concentration, nitric acid concentration, and temperature. (auth)
Date:
October 1, 1961
Creator:
Ondrejcin, R.S.
Object Type:
Report
System:
The UNT Digital Library
Some Metallurgical Applications of Autoradiography
Macro- and high-resolution methods for autoradiography were used to investigate a number of problems concerning the distribution of uranium and other active elements in metal specimens. Illustrations are presented of the behavior of some of these materials with various henting and cooling treatments and in the presence of metals with which intermetallic phases are formed. Techniques are discussed for handling and examining autoradiographic stripping films by means of various types of metallurgical and conventional microscopic equipment. (auth)
Date:
October 1, 1961
Creator:
Adams, M. D. & Steunenberg, R. K.
Object Type:
Report
System:
The UNT Digital Library
THE EXPERIMENTAL BERYLLIUM OXIDE REACTOR. MARITIME GAS-COOLED REACTOR PROGRAM
LIUM OXIDE REACTOR. MARITIME GAS-COOLED The Experimental Beryllium Oxide Reactor, EBOR, will be constructed at the National Reactor Testing Station as the AEC portion of the joint Maritime Administration--AEC Maritime Gas Cooled Reactor Program. The ultimate goal of the Program is the development of nuclear power plants employing a helium cooled and beryllium oxide moderated reactor directly coupled to a closed cycle gas turbine. The objective is to obtain compact nuclear engines suitable for use either in a merchant ship propulsion system or an intermediate size central station power plant in the 20 to 100 Mw(e) size range. The EBOR is a l0 Mw(t) test of the basic fuel element and moderator designs. It is capable of being up-graded in power at a later date to a test of the nuclear reactor turbine concept. The objective of the experiment is outlined. The principal reactor components to be tested and the test facility are described. (auth)
Date:
July 1, 1961
Creator:
Moore, W.C.
Object Type:
Report
System:
The UNT Digital Library
Gamma I. A General Theorem-Proving Program for the IBM 704
GAMMA I is a FORTRAN-compiled program for the IBM 704 Electronic Data- Processing Machine. It embodies a certain general, uniform procedure H of mathematical logic for seeking out a proof of any theorem within any mathematical theory which is given in formal axiomatic form. An extended discussion is provided of the underlying method and of the necessary background of mathematical logic. The program is described in detail. (M.C.G.)
Date:
November 1, 1961
Creator:
Robinson, J.A.
Object Type:
Report
System:
The UNT Digital Library