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Sodium Fluozirconate Precipitation Process for Zirconium Fuels. Part 1. Laboratory Development
Precipitation, evaporation, and extraction feed preparation conditions are established for the removal of zirconium and fluoride from fuel dissolver product solutions by the addition of sodium formate. A sparingly soluble complex fluozirconate is formed. Ninety-five to 99% of the zirconium and fluoride is separated from the uranium losses of 0.1% or less. Chemical material balances, based on experimental data, were developed for two flowsheets. In one flowsheet, sufficient nitric acid is added to the combined wash solution and filtrate produced during the precipitation step to destroy the formate ion (which inhibits uranium extraction) and to prevent post-precipitation during the evaporation of these solutions. The other flowsheet calls for addition of sufficient nitric acid to destroy the formate ion, but not enough to prevent post- precipitation during the concentration step. Post-precipitation removes additional zirconium and fluoride, but necessitates an additional solids- separation step. (auth)
Date:
May 15, 1962
Creator:
Newby, B. J.
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
Spent Fuel Transfer, Storage and Shipment for PL-3
In refueling development studies performed on PL-3 Phase I design, several methods of fuel transfer, storage, and shipment were investigated. An evaluation of the relative merits of the systems and designs under study, as applied to either the BWR or PWR concepts, is made and optimum designs are selected. An analysis of spent fuel shipping cask shielding requirements is presented, along with recommendations for future study in this area. (auth)
Date:
March 1, 1962
Creator:
Hauenstein, G. C. & Pomeroy, D. L.
Object Type:
Report
System:
The UNT Digital Library
Thermonuclear Division Semiannual Progress Report for Period Ending April 30, 1962
Progress is reported on thermonuclear research. Separate abstracts were prepared for 8 of the 10 sections. Design and engineering service reports and notes are given in the remaining sections. (M.C.G.)
Date:
September 12, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
RADIOISOTOPE AND RADIATION APPLICATIONS. Quarterly Progress Report
The study of the mechanism of free-radical formation and decay in polymeric materials was continued and extended to include an investigation of the potential application of this information to the development of novel graft copolymers. The study of postirradiation grafting techniques employing both peroxide initiation and direct grafting was continued. In addition, the effect of molecular weight on site formation was further investigated. Licenses and license applications for approximately 300 by-product material licenses were reviewed to obtain information on environmental conditions of source usage. The feasibility of testing sealed-source response to normal environments by accelerated test procedures was studied. Indications are that the approach will probably not be applicable to either vibration or abrasion stresses but may be for corrosion stresses. (auth)
Date:
October 18, 1962
Creator:
Sunderman, D.N., ed.
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
Reactor Development Program Progress Report, March 1962
ABS>Developmental work is reported on the EBWR and Borax-V other general development work is reported in the area of liquid metal cooled reactors and particularly on the EBR-I and H, and the fast reactor test facility. General reactor technological development is described on applied reactor physics, reactor fuels development, reactor materials development, heat engineering and fluid flow, chemical separations, advanced systems, and nuclear safety. (J.R.D.)
Date:
April 15, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Subsize Izod Specimen Designs for Determining the Notch Toughness of Zircaloy-2
Correlations were made on Zircaloy-2 Izod impact data and Charpy-V drop- weight data. Subsize Izod impact specimens of various geometries and notch configurations and standard ASTM Charpy-V specimens were prepared from bar and plate stock and tested. Drop-weight tests were also conducted and the NDT (nil- ductility transition) temperature was determined for 1/2 in. Zircaloy-2 plate. Results show that the impact properties of Zircaloy-2 are sensitive to hydrogen concentration, specimen and notch geometry, and specimen and notch orientation. No subsize specimen design was found which yielded impact curves similar to those obtained with standard Charpy-V notch specimens, but designs suitable for in- pile testing were found. It was found that Zircaloy-2 has the property of arresting a moving crack even at temperatures of --100 deg C and lower. (P.C.H.)
Date:
October 1, 1962
Creator:
Prislinger, J. J.
Object Type:
Report
System:
The UNT Digital Library
Physics Division Summary Report
The use and operation of the 4.5-Mev Van de Graaff generator ts descrtbed. Sputtering experiments were conducted by bombarding single crystals of electrolytic copper wtth deuterons with energies of 0.8 to 2.5 Mev. The experimental results are discussed on the basis of existing sputtering theories. The kinetic-energy distribution and Boltzmann "temperatures" of most of the fragments of cyanogen under electron impact were determined. A lower limit of 0.05 ev for this temperature'' was also determined for the mass spectrometer. A statistical theory of nuclear forces was developed in close analogy with the statistical mechanics of Gibbs. The theory of Byers and Yang was improved by removing the special assumption of cylindrical symmetry and the assumption of independentparticle motion. The safe assumption of time-reversal invariance was substituted for both. The quantum of trapped flux was found to be independent of the shape of the superconducting ring. The effective charge 2e was seen to result from the two-fold degeneracy induced by time-reversal invariance. It was observed that the same considerations which apply to the problem of flux quantization can be used to elucidate the gauge invariance of the theory of Bardeen, Cooper, and Schrieffer. Differences of total cross sections at high energies …
Date:
January 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Energy Matrices of the f$sup 5$ Electron Configuration
The complete electrostatic and spin-orbit matrices of the f/sup 5/ electron configuration were calculated and are presented tabularly. (auth)
Date:
September 1, 1962
Creator:
Wybourne, B. G.
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
Delayed Failure Hydrogen Embrittlement of Zirconium. Summary Report, September 15, 1961 to September 14, 1962
The extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress was investigated. Susceptibility to time-dependent fracture was evaluated for unalloyed zirconium and Zircaloy-2 with 200 and 500 ppm hydrogen as well as for an experimental Zr Al-Sn-Mo alloy and the Canadian Zr-2.5Nb cladding material. For unalloyed zirconium and Zircaloy-2 containing up to 500 ppm hydrogen, no room-temperature, timedependent fracture occurred which could be definitely attributed to the delayed failure phenomenon; an increased grain size, 20% cold deformation by rolling, or corrosion in 750 deg F steam did not significantly affect this behavior. The curve of applied stress versus time to failure at room temperature for the high-strength Zr-Al-Sn--Mo alloy containing 500 ppm hydrcgen established a strong susceptibility to delayed failure due to hydrogen absorption; studies on vacuum-annealed material showed no failures. Further, reduced temperature indicated that the occurrence of static fatigue is temperature dependent. Data for heattreated Zr 2.5Nb containing 500 ppm hydrogen indicated that this material is moderately sensitive to delayed failure at room temperature; higher hydrogen contents caused a greatly increased susceptibility to time-dependent fracture. (auth)
Date:
October 10, 1962
Creator:
Weinstein, D. & Holtz, F. C.
Object Type:
Report
System:
The UNT Digital Library
Delayed Failure Hydrogen Embrittlement of Zirconium. Quarterly Report No. 1, September 15, 1961 to December 14, 1961
A research program to determine the extent to which Zr and Zircaloy-2 exhibits delayed fnilure (static fatigue) as caused by absorbed H/sub 2/ and applied stress is outlined. Dynamic tensile tests were carried out on Zr and Zircaloy-2 without and wlth 200 ppm H/sub 2/. Preliminary results of a delayed failure investigation suggest that Zr containing 200 ppm H/sub 2/ is relatively insensitive to delayed ailure at room temperature up to 900 hr. (D.L.C.)
Date:
January 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Effects of Temperature on Mechanical Properties of Normal Uranium Dingot
Fatigue properties of normal uranium dingot for rotating beam specimens between 150 and 600 deg C are shown as S-N diagrams and are also given by an empirical equation of the form S = bN/sub m/, where S is the stress, N the number of cycIes, and b and m temperature dependent parameters. Tensile properties for temperatures ranging from 30 to 700 deg C are presented in tabular form and as stress-strain diagrams. All of the properties were found to decrease in value with increasing temperature except that at about 350 deg C they showed some irregularities. These irregularities can possibly be explained by the fact that at lower temperatures deformation by twinning predominates while slipping predominates sbove 350 deg C. (auth)
Date:
January 1, 1962
Creator:
Pederson, K. & Murphy, G.
Object Type:
Report
System:
The UNT Digital Library
GAUGE FOR MEASURING BOW OF TUBES
A mechanical gage was designed to measure the bow over any one-foot length of long cylindrical material. The gage was used successfully for measuring bow in components of tubular fuel elements at the Savannah River Laboratory. (auth)
Date:
October 31, 1962
Creator:
Alewine, G.B.
Object Type:
Report
System:
The UNT Digital Library
STUDIES OF THE SCINTILLATION PROCESS IN CsI(Tl)
The scintillation response of CsI(Tl) crystals, having various thallium contents, was measured for excitation of the crystals by monoenergetic gamma rays, protons, and alpha particles. The investi gation was made to provide a test of some of the features of a theoretical model of the scintillation process in thallium-activated alkali iodides proposed by Murray and Meyer. In order to insure that the results obtained in this program would provide a critical test of the scintillation model, special attention was paid to technical effects which could influence the interpretation of the experimental data. For example, the effect of the pulseanalysis time on the relative scintillation response of CsI(Tl) to various charged parti cles was investigated. In addition, the emission spectra of the CsI(Tl) crystals were measured for excitation by x rays, protons, and alpha particles. The results of the investigation showed that the scintillation efficiency of CsI(Tl) is a continuous function of dE/dx, as assumed in the scintillation model, within the accuracy of the experiments when the effect of delta ravs are considered. This led to the conclusion that the light output of CsI(Tl) crystals is, in general, a nonlinear function of the energy of the particle. The shape of the …
Date:
November 30, 1962
Creator:
Gwin, R. & Murray, R. B.
Object Type:
Report
System:
The UNT Digital Library
AN IBM 7090 FORTRAN PROGRAM FOR ASME UNFIRED PRESSURE VESSEL DESIGN AND PRELIMINARY COST ESTIMATION
An IBM 7090 FORTRAN program was written for the preliminary design and cost estimation of unfired pressure vessels with or without a jacket. Both vessel and jacket designs conform to the 1959 ASME Boiler and Pressure Vessel Code, Section VIII, Unfired Pressure Vessels. Vessels and jackets from 5 in. pipe through 84 in. o.d. and 1/4 in. through 1 1/2 in. in metal thickness may be designed by this program as written. Total vessel cost is the sum of metal and fabrication costs, each on a weight basis. (auth)
Date:
October 17, 1962
Creator:
Prince, C. E. & Milford, R. P.
Object Type:
Report
System:
The UNT Digital Library
Crystallographic D-Space Computer Program
D-Space is a computer program which generates indices (hld), tests for space-group extinctions, and calculates d,'' 1/d/sup 2/, sin theta , sin/sup 2/ theta , sin theta / lambda , sin/sub 2/ theta / lambda /sup 2/, theta , and 2 theta for any crystal system and space group, requiring only the unit cell constants as data input. Optional calculations are the single-crystal angle settings, phi and chi, and various Lorentz and Lorentz-polarization corrections. (auth)
Date:
April 1962
Creator:
Mueller, M. H.; Meyer, E. F. H. & Simonsen, S. H.
Object Type:
Report
System:
The UNT Digital Library
Proceedings of the 1960 Idaho Conference on Reactor Kinetics Held at Sun Valley, Idaho, October 12-14, 1960
>Thirty papers are included on reactor kinetics with emphasis being placed on reactor safety and design considerations resulting from kinetic work. Information is presented on power excursion programs, reactor transfer function determination and application, reactor instability and thermal-hydraulic problems, and analytical methods in reactor kinetics. The accomplishments in the field and areas needing emphasis are discussed and summarized. Constructive suggestions are made on program direction and information dissemination. Separate abstracts were prepared for each paper. (N.W.R.) lOl2 Data and analytical work on various power excursion tests are summarized and discussed in order to show the present position and understanding of reactor kinetics under accident conditions. The results show that our understanding of plate-type, water-moderated systems of the low power research type seem to be in good shape. On the other hand, information on radiolytic gas formation and transient boiling phenomena is not understood too well. Data are primarily presented on safety experiments with SPERT I and KEWB; however, some information is presented on power excursion tests of Borax I, SPERT III, Triga, Treat, and Godiva. Results show that the problem of predicting the response of reactor systems is on a much firmer basis, even without knowing very much about details. …
Date:
July 1, 1962
Creator:
Haire, J. C. & Bright, G. O.
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
Research in Radiobiology. Annual Report of Work in Progress on the Chronic Toxicity Program
Separate abstracts were prepared on 8 sections of this report. Data are also included on the status of dogs at various time intervals following the injection of various doses of Ra/sup 226/, Pu/sup 239/, Ra/sup 228/, Th/sup 228, and Sr/sup 90/. (C. H.)
Date:
March 31, 1962
Creator:
Dougherty, T. F.
Object Type:
Report
System:
The UNT Digital Library
Critical Studies of a Fast Reactor Core Containing Depleted Uranium and Sodium as Diluents. (ZPR-III Assembly 36)
Critical studies were performed with a metallic, fast reactor core designed to snvestigate the effects of replacing highly absorbing U/sup 238/ diluent with high-scattering, lowabsorbing sodium diluent. The fuel was 15.7 wt% enriched U/sup 235/ and the core contained 18.2 vol% sodium and 12.68 vol% stainless steel. The experimental program was designed to measure the effect of the material replacement on spectral indices, which consisted of the standard fission ratios, foil irradiations, and a large number of central reactivity coefficients. Other measurements included the Rossi- alpha , radial fission traverses, and edge reactivity worths of a few samples. (auth)
Date:
January 1962
Creator:
Gasidlo, J. M.; Long, J. K. & McVean, R. L.
Object Type:
Report
System:
The UNT Digital Library
Detailed Stress Analysis of SM-1 Steam Generator Tube Sheet
The detailed stress analysis of the SM-1 steam generator tube sheet showed it to be safe from strain cycling damage. However, the pressure stresses were greater than the yield strength during the hydrostatic test. The differential between pressure stresses and yield strength indicates that some initial deformation may have taken place in the tube sheet. (auth)
Date:
July 11, 1962
Creator:
Busuttil, J. J. & Chittum, R. A.
Object Type:
Report
System:
The UNT Digital Library