Latest content added for UNT Digital Libraryhttps://digital.library.unt.edu/search/?t=fulltext&fq=str_year%3A1963&sort=added_a2017-10-18T07:39:23-05:00UNT LibrariesThis is a custom feed for searching UNT Digital LibraryEnergy Dependence Determinations in the 60-180 KeV Range with an X-Ray Machine of Varying Output2010-02-21T23:09:23-06:00https://digital.library.unt.edu/ark:/67531/metadc13078/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc13078/"><img alt="Energy Dependence Determinations in the 60-180 KeV Range with an X-Ray Machine of Varying Output" title="Energy Dependence Determinations in the 60-180 KeV Range with an X-Ray Machine of Varying Output" src="https://digital.library.unt.edu/ark:/67531/metadc13078/small/"/></a></p><p>Report covering a Victoreen Cavity Chamber which utilizes filtered beams from a 250 KVP, Ox 250 General Electric pulsating industrial X-ray machine. The facility, equipment, and procedure is described.</p>Experimental Radiation Measurements in Conventional Structures: Part 2. Comparison of Measurements in Above-Ground and Below-Ground Structures From Simulated and Actual Fallout Radiation2010-02-21T23:09:23-06:00https://digital.library.unt.edu/ark:/67531/metadc13033/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc13033/"><img alt="Experimental Radiation Measurements in Conventional Structures: Part 2. Comparison of Measurements in Above-Ground and Below-Ground Structures From Simulated and Actual Fallout Radiation" title="Experimental Radiation Measurements in Conventional Structures: Part 2. Comparison of Measurements in Above-Ground and Below-Ground Structures From Simulated and Actual Fallout Radiation" src="https://digital.library.unt.edu/ark:/67531/metadc13033/small/"/></a></p><p>Report concerning the protection offered against radioactive fallout offered by two types of structures at the Nevada Test Site. Differences between above ground and underground structures are measured and compared to data taken from actual fallout conditions.</p>A Computer Program for Calculating Neutron Interaction Between Cylindrical Storage Containers2010-02-21T23:09:23-06:00https://digital.library.unt.edu/ark:/67531/metadc13073/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc13073/"><img alt="A Computer Program for Calculating Neutron Interaction Between Cylindrical Storage Containers" title="A Computer Program for Calculating Neutron Interaction Between Cylindrical Storage Containers" src="https://digital.library.unt.edu/ark:/67531/metadc13073/small/"/></a></p><p>Report containing a computerized means to calculate the neutron interaction between fissionable material contained in cylinders up to an array size of 20 x 20 units.</p>Ionization Chambers for Environmental Radiation Measurements2010-02-21T23:09:23-06:00https://digital.library.unt.edu/ark:/67531/metadc13062/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc13062/"><img alt="Ionization Chambers for Environmental Radiation Measurements" title="Ionization Chambers for Environmental Radiation Measurements" src="https://digital.library.unt.edu/ark:/67531/metadc13062/small/"/></a></p><p>From Introduction: "In this report, a detailed description will be given of each of the ionization chambers used, including in each case a discussion of the methods of calibration and of techniques utilized in inferring dose readings."</p>Determination of Beryllium in Urine by Ion Exchange Separation and Fluorimetric Measurement2010-02-21T23:09:23-06:00https://digital.library.unt.edu/ark:/67531/metadc13080/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc13080/"><img alt="Determination of Beryllium in Urine by Ion Exchange Separation and Fluorimetric Measurement" title="Determination of Beryllium in Urine by Ion Exchange Separation and Fluorimetric Measurement" src="https://digital.library.unt.edu/ark:/67531/metadc13080/small/"/></a></p><p>Report containing a method for the determination of beryllium in urine samples. Contains the necessary materials, apparatus, and reagents, as well as the procedure and its results.</p>Operating Characteristics of the Lauterbach and Dautrebande Aerosol Generators2010-02-21T23:09:23-06:00https://digital.library.unt.edu/ark:/67531/metadc13144/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc13144/"><img alt="Operating Characteristics of the Lauterbach and Dautrebande Aerosol Generators" title="Operating Characteristics of the Lauterbach and Dautrebande Aerosol Generators" src="https://digital.library.unt.edu/ark:/67531/metadc13144/small/"/></a></p><p>From Abstract: "The air flow through the jet, the effect of a pre-humidifier on the water vapor content of the jet air, the cooling effect of the jet air on the generator solution, and the amount of water vapor carried away by the jet air were also determined and the results are discussed."</p>Aeroradioactivity Survey and Geology of the Gnome (Carlsbad) Area, New Mexico and Texas (ARMS-I)2010-02-21T23:09:23-06:00https://digital.library.unt.edu/ark:/67531/metadc13030/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc13030/"><img alt="Aeroradioactivity Survey and Geology of the Gnome (Carlsbad) Area, New Mexico and Texas (ARMS-I)" title="Aeroradioactivity Survey and Geology of the Gnome (Carlsbad) Area, New Mexico and Texas (ARMS-I)" src="https://digital.library.unt.edu/ark:/67531/metadc13030/small/"/></a></p><p>Report regarding an airborne radioactivity survey that took place in the 7,000 square mile area around the GNOME test site near Carlsbad, New Mexico. Topics include the types of bedrock noted in the area as well as their levels of radioactivity.</p>Study of Requirements and Suitability of Available Reactors for Fast Fuel Tests2012-10-17T09:47:01-05:00https://digital.library.unt.edu/ark:/67531/metadc38365/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc38365/"><img alt="Study of Requirements and Suitability of Available Reactors for Fast Fuel Tests" title="Study of Requirements and Suitability of Available Reactors for Fast Fuel Tests" src="https://digital.library.unt.edu/ark:/67531/metadc38365/small/"/></a></p><p>Report issued by the APDA over studies conducted on the requirements of reactors for fuel testing. As stated in the summary, "the purpose of this study is to determine the requirements for radiation space for fast reactor fuel testing and to determine the capability of existing Commission and private test and power reactors to meet these requirements" (p. 7). This report includes tables, and illustrations.</p>Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 19632013-09-20T16:38:33-05:00https://digital.library.unt.edu/ark:/67531/metadc67295/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc67295/"><img alt="Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1963" title="Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1963" src="https://digital.library.unt.edu/ark:/67531/metadc67295/small/"/></a></p><p>Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.</p>Instrumentation and Controls Division Annual Progress Report: for Period Ending September 1, 19622014-01-31T11:57:08-06:00https://digital.library.unt.edu/ark:/67531/metadc100424/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100424/"><img alt="Instrumentation and Controls Division Annual Progress Report: for Period Ending September 1, 1962" title="Instrumentation and Controls Division Annual Progress Report: for Period Ending September 1, 1962" src="https://digital.library.unt.edu/ark:/67531/metadc100424/small/"/></a></p><p>Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.</p>Porosity gain from increase in core radius and fuel mass in Tory II-C2015-07-25T02:21:30-05:00https://digital.library.unt.edu/ark:/67531/metadc681630/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc681630/"><img alt="Porosity gain from increase in core radius and fuel mass in Tory II-C" title="Porosity gain from increase in core radius and fuel mass in Tory II-C" src="https://digital.library.unt.edu/ark:/67531/metadc681630/small/"/></a></p><p>A set of calculations has been done to determine the amount by which the volume of solid material in a Tory II-C core can be reduced with respect to the total core volume. Three separate problems were studied. In each case, some change was made which by itself would increase the K[sub eff] of the reactor. Then, in order to keep K[sub eff] unchanged, a certain amount of core material was removed. The calculations were done by means of the one-dimensional neutronic diffusion code ZOOM. The base problem ZR 1008 on which the variations were made is a cross section of Tory II-C as represented in two dimensions by ANGIE problem RZ 501. The cross section is taken at a distance of 0.3 of the length of the reactor from the front surface, and the Z dimension is adjusted in ZR 1008 so that K[sub eff] is the same as for RZ 501.</p>Control rod studies2015-07-25T02:21:30-05:00https://digital.library.unt.edu/ark:/67531/metadc686072/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc686072/"><img alt="Control rod studies" title="Control rod studies" src="https://digital.library.unt.edu/ark:/67531/metadc686072/small/"/></a></p><p>This study was undertaken to answer questions asked regarding the required rod stroke for control of modified Tory II-C reactors. All problems described were solved with the Angie code and based on Tory-II-C design problems, RZ 501 and RZ 502, representing hot and cold reactors respectively.</p>Yankee Core Evaluation Program Quarterly Progress Report: October-December 19622016-08-02T16:57:59-05:00https://digital.library.unt.edu/ark:/67531/metadc784205/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc784205/"><img alt="Yankee Core Evaluation Program Quarterly Progress Report: October-December 1962" title="Yankee Core Evaluation Program Quarterly Progress Report: October-December 1962" src="https://digital.library.unt.edu/ark:/67531/metadc784205/small/"/></a></p><p>Quarterly report regarding the activities of the Yankee Core Evaluation Program, the purpose of which is to evaluate the performance of the core used in the Yankee Plant and to compare actual performance with predictions, as well as the revision of designs to address any differences between actual and predicted performance.</p>Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits2016-08-15T10:58:28-05:00https://digital.library.unt.edu/ark:/67531/metadc860785/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc860785/"><img alt="Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits" title="Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits" src="https://digital.library.unt.edu/ark:/67531/metadc860785/small/"/></a></p><p>Introduction: The purpose of this experiment is to determine the loss of electrical power output due to operating many unequally-heated cesium diodes, connected in series and parallel circuits.</p>The Diffusion of Lithium in Aluminum2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc865261/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc865261/"><img alt="The Diffusion of Lithium in Aluminum" title="The Diffusion of Lithium in Aluminum" src="https://digital.library.unt.edu/ark:/67531/metadc865261/small/"/></a></p><p>The diffusion of lithium in aluminum was measured at various temperatures with diffusion couples of aluminum-LiAl. The activation energy, E, is 33.3 kcal/mol, and the diffusion factor, Do, is 4.5 cm{sup2}/sec. (auth)</p>Development of Batch Formulation Equations for Graphite Fuel Elements2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc863666/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc863666/"><img alt="Development of Batch Formulation Equations for Graphite Fuel Elements" title="Development of Batch Formulation Equations for Graphite Fuel Elements" src="https://digital.library.unt.edu/ark:/67531/metadc863666/small/"/></a></p><p>The development of equations used for determination .. starting weights of the individual mix batch constituents is presented. Experimental data resulting from batches compounded in this manner are shown for uranium loading, carbon density, and composite density of as graphitized natural uranium loaded fuel elements.</p>BURNOUT CONDITIONS FOR SINGLE ROD IN ANNULAR GEOMETRY, WATER AT 600 TO 1400 PSIA2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc871927/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc871927/"><img alt="BURNOUT CONDITIONS FOR SINGLE ROD IN ANNULAR GEOMETRY, WATER AT 600 TO 1400 PSIA" title="BURNOUT CONDITIONS FOR SINGLE ROD IN ANNULAR GEOMETRY, WATER AT 600 TO 1400 PSIA" src="https://digital.library.unt.edu/ark:/67531/metadc871927/small/"/></a></p><p>Tests were run to determine burnout conditions for sn electrically heated rod in a circular tube with an annular flow path for the upward water flow. The conditions correspond to those which might exist in a reactor core. The burnout results for the basic test geometry (straight concentric annulus) showed that a plot of burnout heat flux vs quality is a straight line with a negative slope, and that the burnout heat flux is increased by a decrease in flow or an increase in pressure, while the hydraulic diameter has a maximum effect on the flux at 0.25 to 0.5 inch. A correlation of the results is given for a certain range of conditions. The following modifications of the basic test geometry were also tested: eccentric rod, simulated spacer, sandblasted rod, and rough liner. The eccentric rod and sandblasted rod decreased the burnout heat flux, while the simulated space had no effect, and the flux for the rough liner is greater than for the smooth liner. The basic test geometry data are compared with other internally heated annular data and with multirod data. (D.L.C.)</p>Comments on Proposed Lasl Ln$sub 2$ System2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc867758/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc867758/"><img alt="Comments on Proposed Lasl Ln$sub 2$ System" title="Comments on Proposed Lasl Ln$sub 2$ System" src="https://digital.library.unt.edu/ark:/67531/metadc867758/small/"/></a></p><p>This report addresses the comments on proposed LASL LN$sub 2$ system.</p>NS Savannah Safeguards Report for 80-MW Operation2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc870224/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc870224/"><img alt="NS Savannah Safeguards Report for 80-MW Operation" title="NS Savannah Safeguards Report for 80-MW Operation" src="https://digital.library.unt.edu/ark:/67531/metadc870224/small/"/></a></p><p>None</p>SNAP (SYSTEMS FOR NUCLEAR AUXILIARY POWER) TECHNICAL BRIEFS. PART 8. AEROSPACE SAFETY2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc870164/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc870164/"><img alt="SNAP (SYSTEMS FOR NUCLEAR AUXILIARY POWER) TECHNICAL BRIEFS. PART 8. AEROSPACE SAFETY" title="SNAP (SYSTEMS FOR NUCLEAR AUXILIARY POWER) TECHNICAL BRIEFS. PART 8. AEROSPACE SAFETY" src="https://digital.library.unt.edu/ark:/67531/metadc870164/small/"/></a></p><p>None</p>Deformation Twinning in Face-Centered Cubic Metals. Technical Report No. 12016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc869128/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc869128/"><img alt="Deformation Twinning in Face-Centered Cubic Metals. Technical Report No. 1" title="Deformation Twinning in Face-Centered Cubic Metals. Technical Report No. 1" src="https://digital.library.unt.edu/ark:/67531/metadc869128/small/"/></a></p><p>A review is presented of work on deformation twinning in fcc metals. Experiments which prove the existence of deformation twins are described, the characteristics of the twins are reviewed, and the stresses required for their production are analyzed. The dislocation models which have been proposed to account for the nucleation of deformation twins are reviewed. A model is proposed for the propagation of twins. (D.L.C.)</p>The Large Component Test Loop-Description and Operating Capabilities2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc871584/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc871584/"><img alt="The Large Component Test Loop-Description and Operating Capabilities" title="The Large Component Test Loop-Description and Operating Capabilities" src="https://digital.library.unt.edu/ark:/67531/metadc871584/small/"/></a></p><p>The Large Component Test Loop is a facility for ASCR providing experimental capacity for subjecting large components, such as moderator assemblies and control rods, to thermal gradients and transients at varying rates of sodium flow to simulate reactor operating conditions. Two separate loops are used for heating and cooling the sodium as the testing is performed. The 3-inch pump loop, modified to operate at 1200 deg F, was operated at a flow of 130 gpm and a head of 25 feet. The 6-inch pump loop, limited to 1000 deg F operation by materials of construction, was operated at a flow of 2000 gpm and head of 65 feet. The rest of the facility has operated satisfactorily at 1200 deg F. (auth)</p>Comments on E-Mad Phase II Drawings Received February 6, 19632017-10-15T22:09:52-05:00https://digital.library.unt.edu/ark:/67531/metadc1022329/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1022329/"><img alt="Comments on E-Mad Phase II Drawings Received February 6, 1963" title="Comments on E-Mad Phase II Drawings Received February 6, 1963" src="https://digital.library.unt.edu/ark:/67531/metadc1022329/small/"/></a></p><p>This document reflects our comments on the drawings and design information that we have received. It is therefore contingent upon the drawings and specifications which we have not as yet received from Vitro Engineering Company.</p>Preliminary study for a destruct system2017-10-15T22:09:52-05:00https://digital.library.unt.edu/ark:/67531/metadc1021691/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1021691/"><img alt="Preliminary study for a destruct system" title="Preliminary study for a destruct system" src="https://digital.library.unt.edu/ark:/67531/metadc1021691/small/"/></a></p><p>None</p>Health physics environmental monitoring semiannual report, January--June 19622017-10-15T22:09:52-05:00https://digital.library.unt.edu/ark:/67531/metadc1027065/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1027065/"><img alt="Health physics environmental monitoring semiannual report, January--June 1962" title="Health physics environmental monitoring semiannual report, January--June 1962" src="https://digital.library.unt.edu/ark:/67531/metadc1027065/small/"/></a></p><p>None</p>Evaluation of ejector systems for ETS-1. Interim report, 1 October 1962-- 31 January 19632017-10-15T22:09:52-05:00https://digital.library.unt.edu/ark:/67531/metadc1023970/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1023970/"><img alt="Evaluation of ejector systems for ETS-1. Interim report, 1 October 1962-- 31 January 1963" title="Evaluation of ejector systems for ETS-1. Interim report, 1 October 1962-- 31 January 1963" src="https://digital.library.unt.edu/ark:/67531/metadc1023970/small/"/></a></p><p>None</p>Derivation of Linearized, Difference-Differential Equations for Analog Computer Studies of Gas-Flow Oscillations2017-10-15T22:09:52-05:00https://digital.library.unt.edu/ark:/67531/metadc1019391/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1019391/"><img alt="Derivation of Linearized, Difference-Differential Equations for Analog Computer Studies of Gas-Flow Oscillations" title="Derivation of Linearized, Difference-Differential Equations for Analog Computer Studies of Gas-Flow Oscillations" src="https://digital.library.unt.edu/ark:/67531/metadc1019391/small/"/></a></p><p>The basic heat transfer and flow equations applicable to studies of flow oscillations in NERVA engines are first linearized, then expressed as difference-differential approximations, and finally written in a form suitable for analog computer solution. Block diagrams are presented which illustrate on analog procedure for solving the linearized, difference-differential equations.</p>Summary report on the re-entry burnup of graphite particles2017-10-15T22:09:52-05:00https://digital.library.unt.edu/ark:/67531/metadc1025781/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1025781/"><img alt="Summary report on the re-entry burnup of graphite particles" title="Summary report on the re-entry burnup of graphite particles" src="https://digital.library.unt.edu/ark:/67531/metadc1025781/small/"/></a></p><p>None</p>Calibration of Control Drums in a Sub-Critical Assembly2017-10-15T22:09:52-05:00https://digital.library.unt.edu/ark:/67531/metadc1017120/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1017120/"><img alt="Calibration of Control Drums in a Sub-Critical Assembly" title="Calibration of Control Drums in a Sub-Critical Assembly" src="https://digital.library.unt.edu/ark:/67531/metadc1017120/small/"/></a></p><p>A method of calibrating control drums in a subcritical assembly with a source is given here as an to WANL- TMI- 458 which discusses the measurement of shutdown reactivity in a subcritical core</p>Comments on E-MAD Phase II drawings received between 2/14/63 and 2/19/632017-10-15T22:09:52-05:00https://digital.library.unt.edu/ark:/67531/metadc1023606/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1023606/"><img alt="Comments on E-MAD Phase II drawings received between 2/14/63 and 2/19/63" title="Comments on E-MAD Phase II drawings received between 2/14/63 and 2/19/63" src="https://digital.library.unt.edu/ark:/67531/metadc1023606/small/"/></a></p><p>This report talks about the Comments on E-MAD Phase II drawings received between 2/14/63 and 2/19/63</p>A Fluid-Bed Process for the Direct Conversion of Uranium Hexafluoride to Uranium Dioxide2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1031060/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1031060/"><img alt="A Fluid-Bed Process for the Direct Conversion of Uranium Hexafluoride to Uranium Dioxide" title="A Fluid-Bed Process for the Direct Conversion of Uranium Hexafluoride to Uranium Dioxide" src="https://digital.library.unt.edu/ark:/67531/metadc1031060/small/"/></a></p><p>A new, dry process for the production of UO/sub 2/ powder from UF/sub 6/ by fluidization and particle-coating techniques was developed. The process involves direct conversion of UF/sub 6/ to a solid, UO/sub 2/F/sub 2/, by hydrolysis with steam and the reduction of the UO/sub 2/F/sub 2/ to the dioxide by reaction with was carried out in 3-in.-dia. Monel reactors. In continuing studies, dense, spheroidal UO/sub 2/ particles in the range --20 +200 mesh are being prepared. A simultaneous (steam and H/sub 2/) reaction procedure at temperatures up to 7OO deg C is being used. Particle densities ranged to 9.75g/ cc or about 89% of theoretical. Sintering in H/sub 2/ at about 1700 deg C for 2.5 hr gave final densities of 10.4 to 16.6 g/cc or up to about 96.5% of theoretical density. (auth)</p>A DISCUSSION AND BIBLIOGRAPHY OF CURRENT LITERATURE CONCERNING VAN ALLEN BELTS FOR USE IN SNAP SPACE ENVIRONMENTAL STUDIES2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1031696/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1031696/"><img alt="A DISCUSSION AND BIBLIOGRAPHY OF CURRENT LITERATURE CONCERNING VAN ALLEN BELTS FOR USE IN SNAP SPACE ENVIRONMENTAL STUDIES" title="A DISCUSSION AND BIBLIOGRAPHY OF CURRENT LITERATURE CONCERNING VAN ALLEN BELTS FOR USE IN SNAP SPACE ENVIRONMENTAL STUDIES" src="https://digital.library.unt.edu/ark:/67531/metadc1031696/small/"/></a></p><p>Discussion of theories on particle motion in electric and magnetic fields precedes examination of theories on the source of the inner and outer Van Allen belts. Theories for the inner belt propose solar cosmic ray injection and galactic cosmic ray injection as the source of the protons. Neutron albedo is particularly examined but seems to be unaccountable for the proton belt. Neutron albedo and injection from the sun are also considered as possible sources of the electrons in the outer belt. Fluctuations, intensities, and distributions of the belts are also discussed, and the connection between the belts and aurora displays is examined. Fluxes, spectra, and particle intensities are displayed, and the effects of magnetic storms on the belts are analyzed. 150 references. (D.C.W.)</p>Neutron Thermalization Programs for the IBM 70902017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1029029/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1029029/"><img alt="Neutron Thermalization Programs for the IBM 7090" title="Neutron Thermalization Programs for the IBM 7090" src="https://digital.library.unt.edu/ark:/67531/metadc1029029/small/"/></a></p><p>A system of six codes is described that permits the solution of a broad class of problems encountered in the study of neutron thermalization, average cross sections, and spectral models. These programs are all compatible with use on MONITOR for the IBM 7090. The Fortran listings are given. (auth)</p>Radiation Survey of the Reactor Vessel Head. Core 1, Seed 3. Test Evaluation2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1028292/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1028292/"><img alt="Radiation Survey of the Reactor Vessel Head. Core 1, Seed 3. Test Evaluation" title="Radiation Survey of the Reactor Vessel Head. Core 1, Seed 3. Test Evaluation" src="https://digital.library.unt.edu/ark:/67531/metadc1028292/small/"/></a></p><p>A detailed radiation survey of the Shippingport Reactor vessel head was made, and the magnitude of the radiation in the vicinity of the vessel head after extended power operation and the effect of normal rod motion and scrams on this magnitude are reported. (L.T.W.)</p>Alpha-Gamma Angular Correlation Measurements With Liquid Sources2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1027835/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1027835/"><img alt="Alpha-Gamma Angular Correlation Measurements With Liquid Sources" title="Alpha-Gamma Angular Correlation Measurements With Liquid Sources" src="https://digital.library.unt.edu/ark:/67531/metadc1027835/small/"/></a></p><p>Alpha-gamma angular correlation measurements were made with solid sources of Am/sup 243/ and with liquid sources containing either Am/sup 243/ or an even-even alpha emitter in dilute perchloric acid solutions. Even-even alpha emitters studied are U/sup 232/, Th/sup 230/, and Ra/sup 226/ . Thicknesses of the soli d sources were controlled so that the neptunium recoils from one source were stopped in Am/sub 2/O/sub 3/, while recoils from the other sources were stopped in the aluminum, gold, or mica backing on which the sources were vaporized. The liquid sources were films consisting of 3 microliters of solution placed between a rubber hydrochloride membrane and a microscope cover glass, 1 cm/sup 2/ in circular cross section. The perchloric acid concentration of the liquid sources ranged from 0.5 to 3.0 molar. All of the angular correlations obtained with solid Am/sup 243/ sources were attenuated, the average attenuation coefficients being 0.29 450 deg C in a 0.01 for sources in which recoils were stopped in Am/sub 2/O/sub 3/, 0.20 450 deg C in a 0.01 for sources in which recoils were stopped in mica, 0.52 450 deg C in a 0.02 for sources in which recoils were stopped in gold, and 0.67 450 deg C in a 0.01 for sources in which recoils were stopped in aluminum. Unattenuated angular correlations were obtained with liquid sources containing Am/sup 243/ in 0.5 M and 1.0 M HClO/sub 4/ . For liquid sources containing Am/sup 243/ in 3.0 M HClO/sub 4/, the correlation was attenuated, with an average attenuation coefficient of 0.86 450 deg C in a 0.01. Attenuated angular correlations were also found with liquid sources containing an even-even nuclide in dilute aqueous solutions The average attenuation coefficients for the even-even nuclide liquid sources were G/sub 2/ = 0.75 450 deg C in a 0.05 and G/sub 4/ = 0.86 450 deg C in a 0.03 for U/sub 232/ , G/sub 2/= 0.64 450 deg C in a 0.06 and G/sub 4/= 0.84 450 deg C in a 0.04 for Th/ sup 230/, and G/sub 2/ = 0.76 450 deg C in a 0.11 and G/sub 4/ = 0.90 450 deg C in a 0.07 for Ra/sup 226/. The postulate that the measured angular correlation function for Am/sup 243/ is attenuated by the same amount as the correlation functions for the even-even nuclides is found to be untenable since it requires unreasonable alpha mixing ratios or unreasonable admixtures of M2 to E1 gamma radiation in the Am/sup 243/ decay process. The attenuation observed with even-even nuclide sources is believed to be consistent with the postulate of a time-dependent electric interaction. 81 references. (auth)</p>Reactor Development Program Progress Report2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1027947/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1027947/"><img alt="Reactor Development Program Progress Report" title="Reactor Development Program Progress Report" src="https://digital.library.unt.edu/ark:/67531/metadc1027947/small/"/></a></p><p>Developmental activities are reported on Borax-V, EBR-I, EBR-II, FARET, general reactor technology, and advanced reactor research. Other work is reported on the Pu recycle program and nuclear safety. (J.R.D.)</p>Reduction of Vapor Carry-Under in Simulated Boiling2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1029225/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1029225/"><img alt="Reduction of Vapor Carry-Under in Simulated Boiling" title="Reduction of Vapor Carry-Under in Simulated Boiling" src="https://digital.library.unt.edu/ark:/67531/metadc1029225/small/"/></a></p><p>The effect on vapor carryunder in simulated boiling caused by insertion in the flow stream of several different geometric configurations and sizes of wire screens is described. The effect on vapor carryunder caused by screen location and mesh size is shown to be closely related to other system variables. The relationship among the most significant variables is shown in a series of graphs. Significant reduction of vapor carryunder is achieved under certain conditions. (auth)</p>Instrumentation and Controls Division Annual Progress Report for Period Ending September 1, 19622017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1025259/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1025259/"><img alt="Instrumentation and Controls Division Annual Progress Report for Period Ending September 1, 1962" title="Instrumentation and Controls Division Annual Progress Report for Period Ending September 1, 1962" src="https://digital.library.unt.edu/ark:/67531/metadc1025259/small/"/></a></p><p>Progress is reported on instrumentation and controls. Topics covered include: electronic systems and components, semiconductor research, radiation monitoring systems, radiation-detectlon instruments and components, data handling and computation, process instrumentation and control systems, process instrumentation development, reactor instrumentation and controls, and support for highvoltage accelerator program. Separate abstracts were prepared for each topic. (M.C.G.)</p>AMF ON-POWER REFUELING SYSTEM FOR A CANDU-TYPE REACTOR. ADAPTER VALVE DEVELOPMENT REPORT2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1025269/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1025269/"><img alt="AMF ON-POWER REFUELING SYSTEM FOR A CANDU-TYPE REACTOR. ADAPTER VALVE DEVELOPMENT REPORT" title="AMF ON-POWER REFUELING SYSTEM FOR A CANDU-TYPE REACTOR. ADAPTER VALVE DEVELOPMENT REPORT" src="https://digital.library.unt.edu/ark:/67531/metadc1025269/small/"/></a></p><p>Development of the reference adapter valve for the alternate on-power refueling machine head used in connection with CANDU-type power reactors is described. Results of valve component testing are included. (J.R.D.)</p>A TRANSFER FUNCTION FOR D.C. OPERATIONAL AMPLIFIERS WITH GENERALIZED EXTERNAL NETWORKS2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1035481/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1035481/"><img alt="A TRANSFER FUNCTION FOR D.C. OPERATIONAL AMPLIFIERS WITH GENERALIZED EXTERNAL NETWORKS" title="A TRANSFER FUNCTION FOR D.C. OPERATIONAL AMPLIFIERS WITH GENERALIZED EXTERNAL NETWORKS" src="https://digital.library.unt.edu/ark:/67531/metadc1035481/small/"/></a></p><p>A transfer function for d-c operational amplifiers with generalized input and feed-back networks is derived by application of network theory. This transfer function, more general than others in common use, applies to three and four-terminal networks. It contains, as a special case, the well-known transfer function for d-c operational amplifiers with two-terminal networks. Examples are given. (auth)</p>TRAJECTORIES FOR A RECTANGULAR MAGNET WITH UNIFORM FIELD2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1036014/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1036014/"><img alt="TRAJECTORIES FOR A RECTANGULAR MAGNET WITH UNIFORM FIELD" title="TRAJECTORIES FOR A RECTANGULAR MAGNET WITH UNIFORM FIELD" src="https://digital.library.unt.edu/ark:/67531/metadc1036014/small/"/></a></p><p>To aid in orientation of a hodoscope system using a rectangular magnet with a uniform field, projections of the trajectory of particles in the horizontal and ventical planes are calculated approximately. Fringing field effects are represented by adding a correction to the length of the magnet and assuming the field to be uniform over the total effective length. The assumption that the source lies in the median plane of the magnet is also used in treating the vertical motion. (D.C.W.)</p>Nucleon-Meson Cascade Calculations: Transverse Shielding for a 45-Gev Electron Accelerator. Part Ii2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1036088/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1036088/"><img alt="Nucleon-Meson Cascade Calculations: Transverse Shielding for a 45-Gev Electron Accelerator. Part Ii" title="Nucleon-Meson Cascade Calculations: Transverse Shielding for a 45-Gev Electron Accelerator. Part Ii" src="https://digital.library.unt.edu/ark:/67531/metadc1036088/small/"/></a></p><p>In a previous report nucleon-meson cascade calculations were carried out for several cases of interest in the design of the transverse shield for the proposed 45-Bev linear electron accelerator at Starford University. In this report results are given for several additional cases. Muon, neutron, pion, and proton intensities as function of energy and distance for varying angles are given. Corresponding doses are also included. (D.C.W.)</p>Scattering of 14-Mev Neutrons From Nitrogen and Oxygen2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1035748/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1035748/"><img alt="Scattering of 14-Mev Neutrons From Nitrogen and Oxygen" title="Scattering of 14-Mev Neutrons From Nitrogen and Oxygen" src="https://digital.library.unt.edu/ark:/67531/metadc1035748/small/"/></a></p><p>The differential cross sections for elastic scattering of 14-Mev neutrons from nitrogen and oxygen were measured in the angular range from 17 to 140 deg , using liquid targets and annular ring geometry. Inelastic scattering to the 2.31 and 3.95-Mev levels in N/sup 14/ and to the levels near 6 and 7 Mev in O/sup 16/ was investigated over a more restricted angular range. The 2.31-Mev level in N/sup 14/ was not excited appreciably, in disagreement with previously reported results. For both elements, the elastic scattering cross sections (determined to an accuracy of 10%) were found to be appreciably higher than the optical model predictions by Rjorklund and Fernbach for scatterirg angles larger than 70 deg . The inelastic cross sections measured are, within experimental accuracy, the same as the corresponding (p,p') cross sections. (auth)</p>A PRELIMINARY EXAMINATION OF THE FORMATION AND UTILIZATION OF TEXTURE AND ANISOTROPY IN ZIRCALOY-22017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1035393/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1035393/"><img alt="A PRELIMINARY EXAMINATION OF THE FORMATION AND UTILIZATION OF TEXTURE AND ANISOTROPY IN ZIRCALOY-2" title="A PRELIMINARY EXAMINATION OF THE FORMATION AND UTILIZATION OF TEXTURE AND ANISOTROPY IN ZIRCALOY-2" src="https://digital.library.unt.edu/ark:/67531/metadc1035393/small/"/></a></p><p>The anisotropy of mechanicai properties in Zircaloy-2 associated with preferred orientation developed during manufacture has caused many difficulties in the fabrication and utilization of mill products. A preliminary examination of the development and utilization of texture preparatory to an experimental study of anisotropy in Zircaloy-2 tubing is presented. The development of preferred orientation during manufacture of Zircaloy-2 plate, strip, and tubing is qualitatively analyzed in terms of the plastic strain undergone, the modes of deformation operative, the existing anisotropy of flow strengths, and the effects of forming forces of the rolls or dies. The problem of forming structural shapes from anisotropic mill products is discussed, and the utilization of the anisotropy of mechanical properties to ease manufacture and to strengthen structures is considered. (auth)</p>Progress report for SNAP 2 nuclear auxiliary power unit development, July-- September 19622017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1035311/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1035311/"><img alt="Progress report for SNAP 2 nuclear auxiliary power unit development, July-- September 1962" title="Progress report for SNAP 2 nuclear auxiliary power unit development, July-- September 1962" src="https://digital.library.unt.edu/ark:/67531/metadc1035311/small/"/></a></p><p>None</p>BASIC NUCLEAR AND REACTOR INFORMATION FOR THE REACTOR OPERATOR2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1035313/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1035313/"><img alt="BASIC NUCLEAR AND REACTOR INFORMATION FOR THE REACTOR OPERATOR" title="BASIC NUCLEAR AND REACTOR INFORMATION FOR THE REACTOR OPERATOR" src="https://digital.library.unt.edu/ark:/67531/metadc1035313/small/"/></a></p><p>Basic nuclear and reactor information for the reactor operator is presented in order that the operator will have some knowledge of safe and efficient operation. Some principles of reactor design, construction, and operation are included. Information is given on fission processes, chain reactions, reactor structural components, auxiliary systems, reactor shielding, reactor temperature and pressure measurement, and nuclear instruments. (N.W.R.)</p>Adaptation of a Commercial Counter X-Ray Diffractometer for Investigations to 3000 C2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1035098/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1035098/"><img alt="Adaptation of a Commercial Counter X-Ray Diffractometer for Investigations to 3000 C" title="Adaptation of a Commercial Counter X-Ray Diffractometer for Investigations to 3000 C" src="https://digital.library.unt.edu/ark:/67531/metadc1035098/small/"/></a></p><p>A General Electric XRD-5 diffractometer equipped with a scintillation counter, a pulse height discriminator, and a modified version of the Model X-86G high-temperature diffractometer attachment, was modified for x-ray diffraction analysis at temperatures up to 3000 deg C. These modifications include frame assemblies, viewing port, filament materials, and thermocouples. (D.L.C.)</p>Pathfinder Atomic Power Plant. Boron Stainless Steel Control Rods for Pathfinder Reactor. Final Summary Report2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1028585/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1028585/"><img alt="Pathfinder Atomic Power Plant. Boron Stainless Steel Control Rods for Pathfinder Reactor. Final Summary Report" title="Pathfinder Atomic Power Plant. Boron Stainless Steel Control Rods for Pathfinder Reactor. Final Summary Report" src="https://digital.library.unt.edu/ark:/67531/metadc1028585/small/"/></a></p><p>An extensive development, fabrication, and design analysis program was completed on 2 wt% boron stainiess steel for Pathfinder boiler and superheater control rods. Results indicated that the control rods will operate satisfactorily in the reactor under all foreseeable conditions. It was concluded that the maximum local burnup on the boiler rods is limited to 1.0 core at.% and the superheater rods to 0.5 core at.% to remain well below the onset of any deleterious effects. All stresses imposed on the material were found to be below yield strength. The deflections were calculated and were not sufficient to restrict any movement of the cruciform during reactor operations and scrams. A welding development program produced a sound fabrication method for producing the control rods. A prototype rod was extensively tested in the hot control rod drive test, including a large number of scrams. The rod showed no deleterious effects. The rods were designed to accommodate any helium release and swelling that may occur. (M.C.G.)</p>BOILING WATER REACTOR TECHNOLOGY STATUS OF THE ART REPORT. VOLUME II. WATER CHEMISTRY AND CORROSION2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1027659/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1027659/"><img alt="BOILING WATER REACTOR TECHNOLOGY STATUS OF THE ART REPORT. VOLUME II. WATER CHEMISTRY AND CORROSION" title="BOILING WATER REACTOR TECHNOLOGY STATUS OF THE ART REPORT. VOLUME II. WATER CHEMISTRY AND CORROSION" src="https://digital.library.unt.edu/ark:/67531/metadc1027659/small/"/></a></p><p>Information concerning the corrosive effects of water in power reactor moderator-coolant systems is presented. The information is based on investigations reported in the unclassified literature believed to be fairly complete to 1959, but less complete since then. The material is presented in sections on water decomposition, water chemistry, materials corrosion, corrosion product deposits, and radioactivity. It is noted that the report is presented as a part of a continuing program in development of less expensive materials for use in reactors. (J.R.D.)</p>PHASE EQUILIBRIA IN THE SYSTEM NaF-UF$sub 4$2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1028654/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1028654/"><img alt="PHASE EQUILIBRIA IN THE SYSTEM NaF-UF$sub 4$" title="PHASE EQUILIBRIA IN THE SYSTEM NaF-UF$sub 4$" src="https://digital.library.unt.edu/ark:/67531/metadc1028654/small/"/></a></p><p>None</p>