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Critical Path Scheduling of ETR and MTR Reactor Shutdowns

Description: Report describing a method for planning shutdown projects and scheduling the manpower to shut down Materials Testing Reactors (MTR) and Engineering Test Reactors (ETR).
Date: January 10, 1962
Creator: Jacobs, R. T. & Myers, L. L.
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Eighth Quarterly Progress Report, April-June 1962

Description: A frequency analysis was made of the VBWR stability test data. Interpretation of the steady-state noise observed in the stability tests involved consideration of several possible sources of excitation. One of these, a theory of water surface waves, is summarized. Visual and destructive examinations were made of selected fuel rods. Fretting corrosion of the Zircaloy-clad fuel rods against stainless steel spacers was observed. Evidence that UO/sub 2/ thermal conductivity increases with time was o… more
Date: July 10, 1962
Creator: Hodde, J. A.
Partner: UNT Libraries Government Documents Department
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SAMOOM code

Description: No Description Available.
Date: October 10, 1962
Creator: Duckworth, G. D. & Sullivan, F. E.
Partner: UNT Libraries Government Documents Department
open access

Monte Carlo status report

Description: No Description Available.
Date: November 10, 1962
Creator: Capo, M.A.
Partner: UNT Libraries Government Documents Department
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Investigation of Thermalstress-Fatigue Behavior of Stainless Steel. The Effects of Gage Length and Specimen Configuration on Thermal-Stress-Fatigue Test Results

Description: The importance of the experimental method to thermalstress-fatigue test results is clarified. It is shown that a significant increase in apparent fatigue life can be obtained by measuring maximum strain per cycle instead of an average strain. Extrapoiation curves are given to convert the litter into the formed. A varying-cross-section specimen of zero'' gage length is shown to allow measurement of true, maximum strain. (auth)
Date: May 10, 1962
Creator: Horton, K. E.
Partner: UNT Libraries Government Documents Department
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The Effect of Radiation and Nitric Acid-Nitrate Salt Solution on Some Non- Metallic Materials

Description: Several plastic materials and one ceramic alumina were tested for possible use as electrical insulators and spacers in an electrolytic dissolver for processing irradiated nuclear fuels. They were first screened for chemical resistance to the boiling dissolver product solution composed of 1 M nitric acid and 75 g/l stainless steel metal components as nitrates. Those that were resistant were then exposed simultaneously to the boiling dissolver product solution and a gamma irradiation field. Value… more
Date: December 10, 1962
Creator: Decker, L. A.
Partner: UNT Libraries Government Documents Department
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HIGH-TEMPERATURE VAPOR-FILLED THERMIONIC CONVERTER. Quarterly Technical Progress Report, July 1 through September 30, 1962

Description: The post-test analysis of Cell E was completed with the exception of the microprobe analysis of the emitter structure. Interpretation of data from the analysis indicated the necessity of improving the cleanliness of future cell assemblies and especially the need for techniques to determine the emitter condition throughout final assembly. A 10 UC-90 ZrC emitter was installed in Cell F. Thermocouple installation and calibration and high-temperature vacuum emission tests are being conducted prior … more
Date: November 10, 1962
Creator: Godsin, W.
Partner: UNT Libraries Government Documents Department
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The Overpressure-Duration Relationship and Lethality in Small Animals. Technical Progress Report

Description: A total of 993 mice, rats, guinea pigs, and rabbits were exposed to sharp-rising overpressures of various short durations. They were mounted on a concrete pad above which high-explosive charges, ranging in weight from 0.50 oz to 64 lbs, were detonated. Pressure-time measurements were obtained with pencil- type and shock-tube piezo-electric gauges on the pad directly beneath the charges. The duration of the blast waves ranged from 0.40 to 6.8 msec. The LD/sub 50/ pressures were calculated for ea… more
Date: September 10, 1962
Creator: Richmond, D. R.; Goldizen, V. C.; Clare, V. R. & White, C. S.
Partner: UNT Libraries Government Documents Department
open access

View Factors for Heat Radiation in Ghgr Core Configuration

Description: An analysis dealing with view factors is presented in an investigation of the overall interchange factors for heat radiation. Examples concerning the EGCR and the Peach Bottom Reactor are included. (J.R.D.)
Date: December 10, 1962
Creator: Landoni, J. A.
Partner: UNT Libraries Government Documents Department
open access

A Mathematical Model for the Solvent Extraction of Uranyl Nitrate and Nitric Acid

Description: A generalized least-squares technique can be used to calculate equilibrium constants in solvent extraction equilibria by minimizing the difference between observed and calculated distribution ratios. The method was successfully applied to the extraction of uranyl nitrate and nitric acid by TBP dissolved in an inert diluent. (auth)
Date: July 10, 1962
Creator: Lietzke, M. H. & Stoughton, R. W.
Partner: UNT Libraries Government Documents Department
open access

The Fabrication and Irradiation Testing of Dispersion-Type BeO-UO$sub 2$ Ceramic Fuel Materials

Description: Considerations affecting the design of dispersion-type ceramic fuel materials are discussed. The results of measurements made to study the effect of fuel loading on the properties of the fuel bodies and the results of irradiation tests of fuel pellets composed of 20 vol% UO/sub 2/ dispersed in BeO are presented. Experience in the fabrication of dispersion-type BeO --UO/sub 2/ ceramic fuel materials is described. From the results obtained, it is believed that BeO --UO/sub 2/ fuel materials of th… more
Date: October 10, 1962
Creator: Johnson, D. E. & Lofftus, F. H.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Unit Operations Section Monthly Progress Report, December 1961

Description: The height of transfer units in a 6-in.-ID foam-liquid column for isotopic exchange or stripping of Sr using Sr/sup 89/ tracer were 1.4 to 4.6 in. Denitration of Th(NO/sub 3/)/sub 4/ in an agitated trough to give thoria for dispersion into a sol is reproducible. The loading of UF/sub 6/ on a single layer of 1/8in. right circular cylinders of NaF in the presence of a flowing UF/ sub 6/-N/sub 2/ stream showed strong dependence on gas concentration in the range of 0.58 to 8.0 mole% UF/sub 6/ and a… more
Date: April 10, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
open access

PROTON RECOIL ENERGY LOSS DISTRIBUTION IN PLANE GEOMETRY

Description: Computations of proton recoil energy losses from neutron irradiation of hydrogenous systems possessing plane symmetry were made for the purpose of fast neutron counter design. A digital computer code was written to carry out the calculations for two irradiation geometries: the neutron beam is assumed to be normally incident upon the system, and the system is exposed to an isotropic flux of neutrons. Numerical results are presented for neutrons of various energies incident on plane radiators of … more
Date: July 10, 1962
Creator: Eldridge, H.B.; Flusser, P.R. & Ritchie, R.H.
Partner: UNT Libraries Government Documents Department
open access

The power output and efficiency of thermionic converters connected in series and parallel circuits--Part I

Description: Optimum and off-optimum performance is experimentally obtained for one of the 10 mil spaced, 7 cm/sup 2/ emitter area, cylindrical geometry thermionic converters to be used in the series and parallel connected thermionic converter experiment. The results are presented as graphs of output voltage vs power input, and power output vs power input. The current is the major parameter in both cases. The data in these forms are used to compute the power output of twin converter circults having unequal … more
Date: April 10, 1962
Creator: Holland, J. W.
Partner: UNT Libraries Government Documents Department
open access

DISCUSSION OF AN ACTIVATION METHOD FOR MEASURING THE RATIO OF U$sup 238$ ABSORPTION TO U$sup 235$ FISSION IN A REACTOR

Description: The theory is presented in detail of an activation method for measuring the ratio of U/sup 238/ absorptions to U/sup 235/ fissions in a nuclear reactor. The origin of the activities is discussed, the equations are given for interpretation of the measurements, and the expected counting rates are computed for a typical experiment in the EGCR. (auth)
Date: August 10, 1962
Creator: Preskitt, C.A.
Partner: UNT Libraries Government Documents Department
open access

PL Final Design Report. Volume 6. Plant Performance Analysis

Description: Data and information are presented concerning analyses of PL-2 transient performance, normal startup and shutdown procedures, and shield design. (J.R.D.)
Date: May 10, 1962
Partner: UNT Libraries Government Documents Department
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