Latest content added for UNT Digital Libraryhttps://digital.library.unt.edu/search/?t=fulltext&fq=untl_decade%3A1960-1969&sort=title&display=grid2022-05-24T06:12:46-05:00UNT LibrariesThis is a custom feed for searching UNT Digital LibraryAn 8-Matrix Theory of the Vertex p - NN Based on the Strip Approximation2022-02-05T09:44:51-06:00https://digital.library.unt.edu/ark:/67531/metadc1254418/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1254418/"><img alt="An 8-Matrix Theory of the Vertex p - NN Based on the Strip Approximation" title="An 8-Matrix Theory of the Vertex p - NN Based on the Strip Approximation" src="https://digital.library.unt.edu/ark:/67531/metadc1254418/small/"/></a></p><p>The present study was motivated by an attempt to understand low energy [formula] scattering within the framework of the bootstrap principle and the un-Reggeized version of the strip approximation. This work attempts to generate low energy [formula] scattering in the p(1,1) and p(3,3) states assuming the potential operating in these states is generated by the exchange of low mass meson states in the crossed t-channel and low mass baryon states in the crossed u channel. In particular, the p-meson is kept in channel t; the p mass and the coupling of [formula] and [formula] appear as parameters. The parameters of the nucleon and (3,3) poles are taken as the elements to be determined by self-consistency.</p>The 25-Inch Liquid Hydrogen Bubble Chamber2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1033687/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1033687/"><img alt="The 25-Inch Liquid Hydrogen Bubble Chamber" title="The 25-Inch Liquid Hydrogen Bubble Chamber" src="https://digital.library.unt.edu/ark:/67531/metadc1033687/small/"/></a></p><p>None</p>30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures2014-09-25T20:32:43-05:00https://digital.library.unt.edu/ark:/67531/metadc100975/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc100975/"><img alt="30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures" title="30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures" src="https://digital.library.unt.edu/ark:/67531/metadc100975/small/"/></a></p><p>Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.</p>40-Mw(e) Prototype High-Temperature Gas-Cooled Reactor Postconstruction Research and Development Program. Quarterly Progress Report for the Period Ending April 30, 19652017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1028744/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1028744/"><img alt="40-Mw(e) Prototype High-Temperature Gas-Cooled Reactor Postconstruction Research and Development Program. Quarterly Progress Report for the Period Ending April 30, 1965" title="40-Mw(e) Prototype High-Temperature Gas-Cooled Reactor Postconstruction Research and Development Program. Quarterly Progress Report for the Period Ending April 30, 1965" src="https://digital.library.unt.edu/ark:/67531/metadc1028744/small/"/></a></p><p>None</p>100-Watt Curium-242 Fueled Thermoelectric Generator--Conceptual Design. SNAP Subtask 5.7 Final Report2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc865460/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc865460/"><img alt="100-Watt Curium-242 Fueled Thermoelectric Generator--Conceptual Design. SNAP Subtask 5.7 Final Report" title="100-Watt Curium-242 Fueled Thermoelectric Generator--Conceptual Design. SNAP Subtask 5.7 Final Report" src="https://digital.library.unt.edu/ark:/67531/metadc865460/small/"/></a></p><p>A thermoelectric generator which produces 100 watts of electrical power continuously over a six-month operational life in a space environment was designed. It employs the heat produced by the decay of Cm/sup 24/ as the source of power. Uniform output over the operational life of the generator is accomplished by means of a thermally actuated shutter which maintains the hot junction temperature of the thermoelectric conventer at a constunt figure by varying the amount of surplus heat which is radiated directly to space from the heat source. The isotopic heat source is designed to safely contain the Cm/sup 242/ under conditions of launch pad abont and rocket failure, but to burn up upon re-entry to the earth's atmosphere from orbital velocity. (W.L.H.)</p>200 Area monthly report No. 4, April 19662018-11-28T14:33:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1389137/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1389137/"><img alt="200 Area monthly report No. 4, April 1966" title="200 Area monthly report No. 4, April 1966" src="https://digital.library.unt.edu/ark:/67531/metadc1389137/small/"/></a></p><p>This monthly report details activities of the 200 Area for the month of April 1966.</p>1559/RE: A CODE TO COMPUTE RESONANCE INTEGRALS IN MIXTURES2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1033315/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1033315/"><img alt="1559/RE: A CODE TO COMPUTE RESONANCE INTEGRALS IN MIXTURES" title="1559/RE: A CODE TO COMPUTE RESONANCE INTEGRALS IN MIXTURES" src="https://digital.library.unt.edu/ark:/67531/metadc1033315/small/"/></a></p><p>The computer program 1559/RE is an experimental IBM-704 code in FORTRAN language for computing the resonance integrals of isotopes in mixtures in the presence of hydrogenic moderation. There may be up to four isotopes, each with no more than 75 resolved resonance levels. Doppler broadening and interference scattering are included No estimate is made of contributions from unresolved resonances. Typical running times are 30 min (with no Doppler broadening) to 90 min (with Doppler broadening) for problems involving 67 levels and unit lethargy widths. Input and theory are discussed, and a typical listing is given. (auth)</p>1965 audit of SRP radioactive waste2015-07-25T02:21:30-05:00https://digital.library.unt.edu/ark:/67531/metadc676234/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc676234/"><img alt="1965 audit of SRP radioactive waste" title="1965 audit of SRP radioactive waste" src="https://digital.library.unt.edu/ark:/67531/metadc676234/small/"/></a></p><p>This report summarizes releases of radioactive waste to the environs of the Savannah River Plant during the calendar year 1965. Total quantities of radioactive waste released from plant startup through 1965 are also reported. Accuracy is not always implied to the degree indicated by the number of significant figures reported. Values were not rounded off, since data will be used in future cumulative summaries. No explanations are given for unusual releases; this information may be found in the Radiological and Environmental Sciences Division Monthly Reports and in the Semi- annual and Annual Environmental Monitoring Reports for 1965.</p>2D PERT. A TWO-DIMENSIONAL PERTURBATION CODE2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1057119/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1057119/"><img alt="2D PERT. A TWO-DIMENSIONAL PERTURBATION CODE" title="2D PERT. A TWO-DIMENSIONAL PERTURBATION CODE" src="https://digital.library.unt.edu/ark:/67531/metadc1057119/small/"/></a></p><p>Given multigroup fluxes and adjoint fluxes of any cylindrical R-Z configuration, 2D PERT may compute: the prompt-neutron lifetime; the relative worth of various delayed neutrons; the integrals of capture, fission, etc., of given materials over any given region; local perturbations, i.e., danger coefflcients; and integrated perturbations, i.e., reactivity effect of uniform variation in the cross sections affecting a whole region. 2D PERT is programmed for a 32K IBM-704 using 3 tape units. The code is written in FORTRAN with the exception of two SAP subroutines. Input fluxes and adjoint fluxes are on tapes which may be obtained either directly from CUREM output or manufactured by a special tape-writing routine. Homogeneous cross sections and variations of these cross sections are either read in as input information or are computed by the code from a microscopic-cross-section library and atomic densities given as input. A combination of these methods may be used. (auth)</p>630A MARITIME NUCLEAR STEAM GENERATOR. Progress Report No. 82016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc866665/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc866665/"><img alt="630A MARITIME NUCLEAR STEAM GENERATOR. Progress Report No. 8" title="630A MARITIME NUCLEAR STEAM GENERATOR. Progress Report No. 8" src="https://digital.library.unt.edu/ark:/67531/metadc866665/small/"/></a></p><p>None</p>ABWR QUARTERLY PROGRESS REPORT, JANUARY 1 TO MARCH 31, 1960. VOLUME I. SL- 1 OPERATIONS AND EVALUATION . VOLUME II. SL-1 HEALTH PHYSICS AND SAFETY2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc866922/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc866922/"><img alt="ABWR QUARTERLY PROGRESS REPORT, JANUARY 1 TO MARCH 31, 1960. VOLUME I. SL- 1 OPERATIONS AND EVALUATION . VOLUME II. SL-1 HEALTH PHYSICS AND SAFETY" title="ABWR QUARTERLY PROGRESS REPORT, JANUARY 1 TO MARCH 31, 1960. VOLUME I. SL- 1 OPERATIONS AND EVALUATION . VOLUME II. SL-1 HEALTH PHYSICS AND SAFETY" src="https://digital.library.unt.edu/ark:/67531/metadc866922/small/"/></a></p><p>The Stationary Low Power Reactor No. 1 is a three Mw boiling water reactor designed to demonstrate the feasibility of a nuclear reactor to supply electrical power and space heat for remote sites. In addition to performance evaluation the facility provides training for military personnel. The reactor was operated for 1159 hr during the quarter for a total core burnup of 20.3%. Power generation was 103.7 Mwd for a total power accumulation of 466.9 Mwd. Eight malfunctions occurred during the quarter for a total unscheduled downtime of 40 hr 44 min, As a result of malfunctions, aluminum keys will be installed on the control rod drives, instrument well covers were removed, and an order has been placed for a station auxiliaries breaker with a higher temperature rating. Data were taken on seven tests during the quarter. Four of these are expected to be completed during the next quarter. All equipment items on order for the SL-1 power extrapolation expansion program are scheduled to be delivered before June 15, 1960. Although condenser dampers and damper controls, process instrumentation, equipment cabinets, and the radiation monitoring equipment have not yet been ordered, construction will not be delayed. The two tie-ins to the existing reactor piping which were required have been made. The engineering and decontamination buildings are nearing completion and will be ready for occupancy in early May. An SL-l operational cost analysis for March of electrical power generated, based on military personnel only, indicated a mil rate of 107. (auth)</p>Accountability equations for plutonium and tritium yields for PT-IP-305-C at 105-H2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1312454/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1312454/"><img alt="Accountability equations for plutonium and tritium yields for PT-IP-305-C at 105-H" title="Accountability equations for plutonium and tritium yields for PT-IP-305-C at 105-H" src="https://digital.library.unt.edu/ark:/67531/metadc1312454/small/"/></a></p><p>It is necessary to provide accountability tables and equations for use in routine product buildup predictions for the duration of the E-N and blanket loads charged under PT-IP-350-C. Recommended values are given.</p>AN ACCURATE CURRENT INTEGRATOR IN THE RANGE OF 10$sup -5$ TO 10$sup -9$ AMPERES2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1028214/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1028214/"><img alt="AN ACCURATE CURRENT INTEGRATOR IN THE RANGE OF 10$sup -5$ TO 10$sup -9$ AMPERES" title="AN ACCURATE CURRENT INTEGRATOR IN THE RANGE OF 10$sup -5$ TO 10$sup -9$ AMPERES" src="https://digital.library.unt.edu/ark:/67531/metadc1028214/small/"/></a></p><p>None</p>Active Metal Reduction of Plutonium Trichloride2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1032894/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1032894/"><img alt="Active Metal Reduction of Plutonium Trichloride" title="Active Metal Reduction of Plutonium Trichloride" src="https://digital.library.unt.edu/ark:/67531/metadc1032894/small/"/></a></p><p>The reduction characteristics of plutonium trichloride are investigated. A flowsheet for batch reduction with Ca is included. (J.R.D.)</p>ACTIVITY DUE TO N$sup 16$ AND N$sup 17$ IN THE HFIR PRIMARY COOLANT2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc870021/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc870021/"><img alt="ACTIVITY DUE TO N$sup 16$ AND N$sup 17$ IN THE HFIR PRIMARY COOLANT" title="ACTIVITY DUE TO N$sup 16$ AND N$sup 17$ IN THE HFIR PRIMARY COOLANT" src="https://digital.library.unt.edu/ark:/67531/metadc870021/small/"/></a></p><p>The concentrations of and activities due to N/sup 16/ and N/sup 17/ in the HFIR primary coolant water were calculated. At the pressure vessel exit, the N/sup 16/ activity is 3.9 x 10/sup 6/ dis/secml and the N/sup 17/ activity is 6.9 x 10/sup 2/ dis/sec-ml. Comparison of the N/sup 16/ activity with the data obtained from the ORR water system indicates that the calculated results are slightly conservative. (auth)</p>Additional test on notched beryllium at 140$sup 0$R (EML-82)2017-10-15T22:09:52-05:00https://digital.library.unt.edu/ark:/67531/metadc1018354/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1018354/"><img alt="Additional test on notched beryllium at 140$sup 0$R (EML-82)" title="Additional test on notched beryllium at 140$sup 0$R (EML-82)" src="https://digital.library.unt.edu/ark:/67531/metadc1018354/small/"/></a></p><p>None</p>Adjustment of total control parameters for C Reactor2018-11-28T14:33:49-06:00https://digital.library.unt.edu/ark:/67531/metadc1342101/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1342101/"><img alt="Adjustment of total control parameters for C Reactor" title="Adjustment of total control parameters for C Reactor" src="https://digital.library.unt.edu/ark:/67531/metadc1342101/small/"/></a></p><p>The three alterations discussed in this report have an effect on the parameters used in Total Control Calculations for C Reactor: Conversion to smaller diameter and shorter vertical safety rods in six outer control channels; installation of forty-four overbored tubes with short fuel charges in the flat zone and an associated increase in spike enrichment; and centralization of the enrichment ring into a three-lattice unit width in place of three and one-half lattice units previously in use. New parameters are derived in this document for future total control calculations.</p>ADVANCED BONUS CORE DEVELOPMENT PROGRAM. Quarterly Progress Report No. 5, December 1964-February 19652017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1034740/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1034740/"><img alt="ADVANCED BONUS CORE DEVELOPMENT PROGRAM. Quarterly Progress Report No. 5, December 1964-February 1965" title="ADVANCED BONUS CORE DEVELOPMENT PROGRAM. Quarterly Progress Report No. 5, December 1964-February 1965" src="https://digital.library.unt.edu/ark:/67531/metadc1034740/small/"/></a></p><p>None</p>Advanced, graphite-matrix, dispersion-type fuel systems. First annual report, April 1, 1962--March 31, 19632017-10-15T22:09:52-05:00https://digital.library.unt.edu/ark:/67531/metadc1020034/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1020034/"><img alt="Advanced, graphite-matrix, dispersion-type fuel systems. First annual report, April 1, 1962--March 31, 1963" title="Advanced, graphite-matrix, dispersion-type fuel systems. First annual report, April 1, 1962--March 31, 1963" src="https://digital.library.unt.edu/ark:/67531/metadc1020034/small/"/></a></p><p>Declassified 4 Sep 1973. A hot-working device for compression of graphite bodies was used to deform cylindrical specimens of matrix graphite containing ZrC or UC-ZrC particles to strains of the order of 30% at temperatures of 2400 to 2900 deg C. The graphite bodies containing ZrC particles (chosen as representative carbide particles) were found to be more plastic near 2500 deg C than similar bodies containing no carbide particles. Microradiographic techniques were used to determine diffusion coefficients of U and Th on actual coated particles by nondestructive means. A tentative energy of activation for the migration of uranium from UC/sub 2/ particles into PyC coatings was determined over the temperature range 1850 to 2300 deg C. The penetration of U into the coatings is not uniform but occurs radially in localized positions, and then spreads circumferentially, creating a banded structure. These results show the importance of the structure of PyC in regard to the diffusion of both fuel and fission-product materials. It was also observed that the diffusion of U is considerably more rapid in the direction parallel to the layer planes in the PyC than it is in the perpendicular direction. Tests with PyC-coated (U, Zr)C particles in graphite-matrix compacts showed that the addition of Zr to the uranium carbide greatly improves the thermal stability. In general, the coatings on these particles retained their integrity for several hours at 2300 and 2500 deg C. (29 figs) (DLC)</p>Advanced Nuclear Rocket Materials Research2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1029215/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1029215/"><img alt="Advanced Nuclear Rocket Materials Research" title="Advanced Nuclear Rocket Materials Research" src="https://digital.library.unt.edu/ark:/67531/metadc1029215/small/"/></a></p><p>A number of metals, carbides, nitrides, oxides, borides, and uranium gulfides are briefly evaluated concerning their possible applications as advanced nuclear rocket materials. (R.J.S.)</p>Aeroradioactivity Survey and Related Surface Geology of Parts of the Los Angeles Region, California (ARMS-I)2010-02-21T23:09:23-06:00https://digital.library.unt.edu/ark:/67531/metadc13029/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc13029/"><img alt="Aeroradioactivity Survey and Related Surface Geology of Parts of the Los Angeles Region, California (ARMS-I)" title="Aeroradioactivity Survey and Related Surface Geology of Parts of the Los Angeles Region, California (ARMS-I)" src="https://digital.library.unt.edu/ark:/67531/metadc13029/small/"/></a></p><p>Report regarding an airborne gamma-radioactivity survey that took place in the 2,800 square mile area around the Los Angeles region in California. Topics include the types of bedrock noted in the area as well as their levels of radioactivity.</p>Aeroradioactivity Survey and Related Surface Geology of Parts of the San Francisco Region, California (ARMS-I)2021-01-12T15:48:02-06:00https://digital.library.unt.edu/ark:/67531/metadc1202695/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1202695/"><img alt="Aeroradioactivity Survey and Related Surface Geology of Parts of the San Francisco Region, California (ARMS-I)" title="Aeroradioactivity Survey and Related Surface Geology of Parts of the San Francisco Region, California (ARMS-I)" src="https://digital.library.unt.edu/ark:/67531/metadc1202695/small/"/></a></p><p>This report follows an aeroradioactivity survey that took place in the San Francisco region, California.</p>Aerospace Nuclear Safety Program at Sandia Corporation. Summary of a Speech2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1032913/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1032913/"><img alt="Aerospace Nuclear Safety Program at Sandia Corporation. Summary of a Speech" title="Aerospace Nuclear Safety Program at Sandia Corporation. Summary of a Speech" src="https://digital.library.unt.edu/ark:/67531/metadc1032913/small/"/></a></p><p>This report describes research, development, support, and test activities in the Sandia Laboratory Aerospace Nuclear Safety Program.</p>Alloying Characteristics of the Rare Earth Elements with the Transition Elements2019-01-12T16:41:59-06:00https://digital.library.unt.edu/ark:/67531/metadc1403910/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1403910/"><img alt="Alloying Characteristics of the Rare Earth Elements with the Transition Elements" title="Alloying Characteristics of the Rare Earth Elements with the Transition Elements" src="https://digital.library.unt.edu/ark:/67531/metadc1403910/small/"/></a></p><p>This report summarizes the technical progress on the subject contract for the period March 15 to May 14 1963.</p>Alpha Particle Ionization of Argon Mixtures--Further Study of the Role of Excited States2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1025359/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1025359/"><img alt="Alpha Particle Ionization of Argon Mixtures--Further Study of the Role of Excited States" title="Alpha Particle Ionization of Argon Mixtures--Further Study of the Role of Excited States" src="https://digital.library.unt.edu/ark:/67531/metadc1025359/small/"/></a></p><p>BS>The average energy required to form an ion pair, W, when alpha particles are absorbed in mixtures of argon with other gases is studied. The other gases were selected on the basis of their ionization potentials. One group consists of representative gases that have ionization potentials below that of Ar (15.77 ev) and above the doublet metastable state of Ar (11.49 and 11.66 ev). This list includes methane, carbon dioxide, nitrous oxide, xenon, and krypton. The other group of special interest consists of some gases with ionization potentials below the metastable state of Ar. All gases tested in these two groups cause an increase in ionization, i e., a decrease in W, when added to argon. As an illustration of this effect, the addition of 1/2% of acetylene to Ar will increase the ionization by 23% The experimental data, i.e., W as a function of relative concentration of the two gases, were fitted to a model in which it is assumed that energy is transferred from two excited levels in argon to the additive gases in collision processes. Good agreement between the experimental data and calculations based on the model is taken as additional evidence that the excited state notion is correct. A quantity of particular interest, the ionization efficiencies for the additive gases, was derived from the data fitting procedure and compared with those found in photoionization studies in a few of the cases. (auth)</p>Aluminum Alloy Work at Hanford2022-02-05T19:03:42-06:00https://digital.library.unt.edu/ark:/67531/metadc1255646/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1255646/"><img alt="Aluminum Alloy Work at Hanford" title="Aluminum Alloy Work at Hanford" src="https://digital.library.unt.edu/ark:/67531/metadc1255646/small/"/></a></p><p>Investigation of aqueous and steam corrosion at elevated temperature has been carried on at Hanford for several tears. A number of reports have been published on various phases of the corrosion program but, except for monthly reports, little has been written on the progress of the Corrosion and Coatings Operation alloy development program. This interim report will outline the more important current phases of the aluminum alloy program.</p>Analog Computer Study of the MSR-ORR in-Pile Pressurized Water Loop No. 12016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc871426/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc871426/"><img alt="Analog Computer Study of the MSR-ORR in-Pile Pressurized Water Loop No. 1" title="Analog Computer Study of the MSR-ORR in-Pile Pressurized Water Loop No. 1" src="https://digital.library.unt.edu/ark:/67531/metadc871426/small/"/></a></p><p>A study of the dynamic behavior of the Merchant Ship Reactor Pressurized Water Loop was made using the Reactor Controls Analog Facility. Computer curves show the predicted response of the loop temperatures to normal load changes and component failure accidents. Except for complete flow stoppage, which was not investigated here, the safety system was shown to be adequate in curbing loop temperature excursions due to postulated accidents. (auth)</p>Analysis of alternatives: Plutonium button-line improvements2018-11-03T11:47:27-05:00https://digital.library.unt.edu/ark:/67531/metadc1315152/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1315152/"><img alt="Analysis of alternatives: Plutonium button-line improvements" title="Analysis of alternatives: Plutonium button-line improvements" src="https://digital.library.unt.edu/ark:/67531/metadc1315152/small/"/></a></p><p>Reduction of Pu nitrate solution to metal is accomplished in the button line portion of the Remote Mechanical Line. Several areas of deficiency exist in the facility, which must be corrected in order to maintain continuity. In December 1963, a study was undertaken to define and evaluate the operational and economic parameters pertinent to deciding to improve or replace the button line. This paper documents the study and presents the conclusions and recommendations.</p>Analysis of LASL Core Bundling Pressure Test2017-10-15T22:09:52-05:00https://digital.library.unt.edu/ark:/67531/metadc1017715/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1017715/"><img alt="Analysis of LASL Core Bundling Pressure Test" title="Analysis of LASL Core Bundling Pressure Test" src="https://digital.library.unt.edu/ark:/67531/metadc1017715/small/"/></a></p><p>This is an analysis, based on a test conducted by LASL personnel, to determine whether relative expansion of two pieces of graphite under bundling loads would result in failure of the graphite.</p>ANALYSIS OF PERFORMANCE OF A ROCKET-BORNE RETARDING POTENTIAL ANALYZER. Final Report2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1029252/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1029252/"><img alt="ANALYSIS OF PERFORMANCE OF A ROCKET-BORNE RETARDING POTENTIAL ANALYZER. Final Report" title="ANALYSIS OF PERFORMANCE OF A ROCKET-BORNE RETARDING POTENTIAL ANALYZER. Final Report" src="https://digital.library.unt.edu/ark:/67531/metadc1029252/small/"/></a></p><p>None</p>Analysis of Pressure Drop and Heat Transfer of a Pebble-Bed-Storage Heater for a Hypersonic Wind Tunnel2016-09-15T23:48:09-05:00https://digital.library.unt.edu/ark:/67531/metadc304200/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc304200/"><img alt="Analysis of Pressure Drop and Heat Transfer of a Pebble-Bed-Storage Heater for a Hypersonic Wind Tunnel" title="Analysis of Pressure Drop and Heat Transfer of a Pebble-Bed-Storage Heater for a Hypersonic Wind Tunnel" src="https://digital.library.unt.edu/ark:/67531/metadc304200/small/"/></a></p><p>Abstract: "The pressure drop and the time-temperature variation of the air test medium and heat storage material in a pebble-bed heater (designed for intermittent hypersonic wind-tunnel operation at test section Mach numbers of 4 to 11) are presented."</p>Analysis of Six-Bar Linkage Using Digital Computer2021-03-24T08:14:51-05:00https://digital.library.unt.edu/ark:/67531/metadc784083/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc784083/"><img alt="Analysis of Six-Bar Linkage Using Digital Computer" title="Analysis of Six-Bar Linkage Using Digital Computer" src="https://digital.library.unt.edu/ark:/67531/metadc784083/small/"/></a></p><p>Summary. The analysis of the motion of a six-bar linkage is difficult because of the large number of variables involved and the large number of calculations that have to be made for each position of the linkage. If a digital computer is used to make the calculations required for a multi-position analysis of a mechanism, it is feasible to design by analyzing a large numbers of similar linkages and selecting the optimum configuration. In this paper expressions have been derived for the output angle as a function of the input angle and the transmission angle as a function of the input angle for any single-degree-of-freedom six-bar linkage for which the parameters are known An example showing the usefulness of a six-bar computer program as a mechanism design tool is discussed.</p>Analysis of the engine resonance survey in the transverse direction at 3$sup 0$-45' (series I) of the vibration survey of XECF in ETS-12017-10-15T22:09:52-05:00https://digital.library.unt.edu/ark:/67531/metadc1018580/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1018580/"><img alt="Analysis of the engine resonance survey in the transverse direction at 3$sup 0$-45' (series I) of the vibration survey of XECF in ETS-1" title="Analysis of the engine resonance survey in the transverse direction at 3$sup 0$-45' (series I) of the vibration survey of XECF in ETS-1" src="https://digital.library.unt.edu/ark:/67531/metadc1018580/small/"/></a></p><p>This report was prepared as an account of work sponsored by an agency of the United States Government.</p>Analysis of the Need for Agena Command Destruct and/or Generator Eject Systems on the Nimbus B/Snap-19 Mission2016-09-21T02:29:59-05:00https://digital.library.unt.edu/ark:/67531/metadc877177/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc877177/"><img alt="Analysis of the Need for Agena Command Destruct and/or Generator Eject Systems on the Nimbus B/Snap-19 Mission" title="Analysis of the Need for Agena Command Destruct and/or Generator Eject Systems on the Nimbus B/Snap-19 Mission" src="https://digital.library.unt.edu/ark:/67531/metadc877177/small/"/></a></p><p>This report evaluates from a safety viewpoint the need for Agena command destruct and/or command or thermal generator eject-systems on the Nimbus B/SNAP-19 mission.</p>Analysis of the stored energy distribution in D-reactor2018-07-03T08:14:20-05:00https://digital.library.unt.edu/ark:/67531/metadc1186885/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1186885/"><img alt="Analysis of the stored energy distribution in D-reactor" title="Analysis of the stored energy distribution in D-reactor" src="https://digital.library.unt.edu/ark:/67531/metadc1186885/small/"/></a></p><p>The purpose of this document is to characterize, as completely as possible, the stored energy distribution in D Reactor as of March 1958, the date of the last stored energy survey and to estimate the temperature rises which can be expected to occur during a stored energy release. D Reactor was chosen for this study only because it represents one of the oldest operating Hanford reactors and not because of any circumstances peculiar to this reactor. 14 refs., 13 figs.</p>ANALYTICAL STUDY OF HEAT TRANSFER TO LIQUID METALS IN CROSS FLOW THROUGH ROD BUNDLES. PART II2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc866961/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc866961/"><img alt="ANALYTICAL STUDY OF HEAT TRANSFER TO LIQUID METALS IN CROSS FLOW THROUGH ROD BUNDLES. PART II" title="ANALYTICAL STUDY OF HEAT TRANSFER TO LIQUID METALS IN CROSS FLOW THROUGH ROD BUNDLES. PART II" src="https://digital.library.unt.edu/ark:/67531/metadc866961/small/"/></a></p><p>None</p>ANGULAR DISTRIBUTION OF FRAGMENTS FROM FISSION INDUCED BY HEAVYIONS IN GOLD AND BISMUTH2016-09-27T01:39:22-05:00https://digital.library.unt.edu/ark:/67531/metadc897439/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc897439/"><img alt="ANGULAR DISTRIBUTION OF FRAGMENTS FROM FISSION INDUCED BY HEAVYIONS IN GOLD AND BISMUTH" title="ANGULAR DISTRIBUTION OF FRAGMENTS FROM FISSION INDUCED BY HEAVYIONS IN GOLD AND BISMUTH" src="https://digital.library.unt.edu/ark:/67531/metadc897439/small/"/></a></p><p>We present the results of measurements of the angular distribution of fission fragments produced by irradiation of Au{sup 197} and Bi{sup 209} with various heavy ions. The projectiles, B{sup 11}, C{sup 12}, N{sup 14}, and O{sup 16}, had energies from a few MeV above the Coulomb barrier to 10.4 MeV per nucleon. The gross features of these results can be explained by use of a model and parameters that have been used by others to account for angular distributions of fission fragments from helium-ion bombardments. In detail, however, these results appear to indicate that the models used to predict the average value of the angular momentum of the compound nucleus give values too low near the Coulomb barrier. Furthermore, at high bombarding energies it is necessary to consider the fact that appreciable direct interaction is taking place.</p>Angular Distribution of Neutrons Produced by 40- and 80-Mev /cap alpha/ Particles on a Thick Tantalum Target2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc870223/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc870223/"><img alt="Angular Distribution of Neutrons Produced by 40- and 80-Mev /cap alpha/ Particles on a Thick Tantalum Target" title="Angular Distribution of Neutrons Produced by 40- and 80-Mev /cap alpha/ Particles on a Thick Tantalum Target" src="https://digital.library.unt.edu/ark:/67531/metadc870223/small/"/></a></p><p>None</p>ANNEALING OF GAMMA RAY INDUCED CHANGES IN ANTIMONY DOPED GERMANIUM2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1028907/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1028907/"><img alt="ANNEALING OF GAMMA RAY INDUCED CHANGES IN ANTIMONY DOPED GERMANIUM" title="ANNEALING OF GAMMA RAY INDUCED CHANGES IN ANTIMONY DOPED GERMANIUM" src="https://digital.library.unt.edu/ark:/67531/metadc1028907/small/"/></a></p><p>An investigatiori of the annealing of the radioinduced carrier concentration change in Sb-doped Ge in the range 370 to 455 l K was made. The irradiations were conducted at liquid nitrogen temperature using Co/ sup 60/ gamma irradiation. A model that explains the observed behavior is presented. On the basis of the model, the observed annealing consists of vacancy diffusion simultaneously to impurity sites and annihilation centers. Analysis of the activation energy for the annealing process yields values of 0.8 to 1.4 ev in agreement with the range of energies that were attributed to vacancy motion but that cannot be resolved into unique components. The complex activation energy is explained by the model in terms of the impurity concentration. It was observed that the change in carrier concentration saturates before complete annealing is achieved. The saturation, which is stable for further annealing at higher temperatures, is also explained in terms of the model. The vacancies are considered to diffuse to annihilation centers, such as dislocation lines, and to the site adjacent to an Sb atom. Those that go to an Sb are trapped. The Sb- vacancy complex can break up to supply a vacancy back to the system or can trap an additional vacancy producing an Sbdivacancy complex. The Sb-divacancy complex is stable for the temperature range considered. The Sb-vacancy reaction comes into equilibrium very quickly compared to the annihilation process. (auth)</p>Annual Report of ICPP Analytical Section for 19612018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1061184/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1061184/"><img alt="Annual Report of ICPP Analytical Section for 1961" title="Annual Report of ICPP Analytical Section for 1961" src="https://digital.library.unt.edu/ark:/67531/metadc1061184/small/"/></a></p><p>Information of interest to analytical chemists is presented in a report containing both positive and negative results obtained in a total of 58,467 determinations. The data and information are presented in sections concernlng the work of the shift laboratory, special analysis laboratory, spectral analytical group, analytical development group, quality control and standards laboratory, and analytical service for EOCR. Details of methods added to the ICPP analytical manual, and to the ICPP analytical radiochemlcal manual are included. (J.R.D.)</p>Annual Report on Contract AEC AT(11-1) 34 p107B Between the U.S. Atomic Energy Commission and The University of California, Riverside: 19672018-07-05T23:11:53-05:00https://digital.library.unt.edu/ark:/67531/metadc1212002/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1212002/"><img alt="Annual Report on Contract AEC AT(11-1) 34 p107B Between the U.S. Atomic Energy Commission and The University of California, Riverside: 1967" title="Annual Report on Contract AEC AT(11-1) 34 p107B Between the U.S. Atomic Energy Commission and The University of California, Riverside: 1967" src="https://digital.library.unt.edu/ark:/67531/metadc1212002/small/"/></a></p><p>Work that has been carried out in several areas of High Energy Physics is described. Visual techniques are used. For the study of the three-pion decay of the K/sup +/ meson, bubble chamber and emulsion methods are used to complement each other, particularly for the tau' mode. Several separate bubble chamber experiments in ..pi../sup +/p, anti pp and K/sup -/p interactions are also described, and the large effort devoted to computer reprogramming for the data analysis indicated. Two emulsion research projects are also described which have for their purpose the study of electromagnetic processes induced by 16 BeV electrons and the study of hypernuclei by K/sup -/ mesons. For the latter work high speed computer methods have been successfully applied to the analysis of the product hypernuclei. These programs of work have not been under way long enough for the main results yet to be available, but some preliminary data have been published and several reports on data analysis and related subjects have been prepared.</p>Annual Technical Progress Report, AEC Unclassified Programs: Fiscal Year 19682020-09-18T21:18:22-05:00https://digital.library.unt.edu/ark:/67531/metadc1392996/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1392996/"><img alt="Annual Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968" title="Annual Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968" src="https://digital.library.unt.edu/ark:/67531/metadc1392996/small/"/></a></p><p>Annual report with the objectives of evaluating, producing, and maintaining an up-to-date set of basic nuclear data; producing and evaluating multigroup constants; and improving of present day methods of neutronic calculations as related to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.</p>ANPP Code Development Program: An Experimental Program on Water-Moderated Arrays of Uranium and Stainless Steel2016-07-08T20:07:18-05:00https://digital.library.unt.edu/ark:/67531/metadc303760/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc303760/"><img alt="ANPP Code Development Program: An Experimental Program on Water-Moderated Arrays of Uranium and Stainless Steel" title="ANPP Code Development Program: An Experimental Program on Water-Moderated Arrays of Uranium and Stainless Steel" src="https://digital.library.unt.edu/ark:/67531/metadc303760/small/"/></a></p><p>From summary: This report describes an experimental study performed on critical arrays of water-moderated, flat plate, laminated fuel bundles. The experiments were performed in support of analytical studies undertaken in the ANPP Code Development Program. The fuel bundles were built up using fully enriched uranium metal foils, stainless steel plates and boron stainless steel plates.</p>Application of Boron Carbide Nickel Dispersion to a Prototype Control Rod2022-05-24T06:12:46-05:00https://digital.library.unt.edu/ark:/67531/metadc1257998/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1257998/"><img alt="Application of Boron Carbide Nickel Dispersion to a Prototype Control Rod" title="Application of Boron Carbide Nickel Dispersion to a Prototype Control Rod" src="https://digital.library.unt.edu/ark:/67531/metadc1257998/small/"/></a></p><p>Previously reported results on the testing of small samples of boron carbide dispersed in nickel by electrolytic codeposition were adequately encouraging to lead to the development of a prototype control rod for operation in the Vallecitos Boiling Water Reactor. The operation of the control rod has been entirely satisfactory.</p>APPROXIMATE SOLUTIONS OF SYSTEMS OF NON-LINEAR EQUATIONS2017-10-18T07:39:23-05:00https://digital.library.unt.edu/ark:/67531/metadc1028590/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1028590/"><img alt="APPROXIMATE SOLUTIONS OF SYSTEMS OF NON-LINEAR EQUATIONS" title="APPROXIMATE SOLUTIONS OF SYSTEMS OF NON-LINEAR EQUATIONS" src="https://digital.library.unt.edu/ark:/67531/metadc1028590/small/"/></a></p><p>None</p>Aqueous Corrosion of Magnesium Alloys2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc864166/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc864166/"><img alt="Aqueous Corrosion of Magnesium Alloys" title="Aqueous Corrosion of Magnesium Alloys" src="https://digital.library.unt.edu/ark:/67531/metadc864166/small/"/></a></p><p>BS>The aqueous corrosion of Mg alloys was investigated at 53 to 150 deg C. Corrosion rates rose rapidly with temperature, reaching about 3 mils per day at 150 deg C for AZ-31 STAMg-2.5 to 3.5 wt.% Al-0.7 to 1.3 wt.% Zn-0.2 wt.% Mn!. Additions of small amounts of Cu and/or Ni to the basic AZ-31 composition reduced the corrosion rate at 150 deg by a factor of about two. Sn may be advantageously substituted for Zn in AZ-31. Control of the pH in the range between 6 and 7 and maintenance of a fluoride concentration in the range between 1 and 10 ppm reduced the corrosion rate of AZ-31 to about 0.1 mil per day at 150 deg C. (auth)</p>Area reduction measurements of fractured tensile specimens2016-09-16T00:32:18-05:00https://digital.library.unt.edu/ark:/67531/metadc863106/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc863106/"><img alt="Area reduction measurements of fractured tensile specimens" title="Area reduction measurements of fractured tensile specimens" src="https://digital.library.unt.edu/ark:/67531/metadc863106/small/"/></a></p><p>This report describes the procedures and techniques involved in area reduction measurements of fractured tensile specimens.</p>Arguello Area (ARMS-II)2010-02-21T23:09:23-06:00https://digital.library.unt.edu/ark:/67531/metadc13052/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc13052/"><img alt="Arguello Area (ARMS-II)" title="Arguello Area (ARMS-II)" src="https://digital.library.unt.edu/ark:/67531/metadc13052/small/"/></a></p><p>"An Aerial Radiographic Measuring Survey (ARMS) of the Arguello area was made for the Civil Effects Test Operations, Division of Biology and Medicine, U.S. Atomic Energy Commission, by Edgerton, Germeshausen & Grier, Inc.(EG&G), between Apr. 5 and Apr. 29, 1962. The survey was part of a nationwide program to measure the present environmental levels of gamma radiation" (p. 5).</p>ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. GCRE-I HAZARDS SUMMARY REPORT. ADDENDUM III2018-01-22T07:23:21-06:00https://digital.library.unt.edu/ark:/67531/metadc1055184/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1055184/"><img alt="ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. GCRE-I HAZARDS SUMMARY REPORT. ADDENDUM III" title="ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. GCRE-I HAZARDS SUMMARY REPORT. ADDENDUM III" src="https://digital.library.unt.edu/ark:/67531/metadc1055184/small/"/></a></p><p>The hazards evaluation was modified to reflect certain changes made to the equipment as a result of operating experience. These changes included: the addition of a startup interlock circuit; the modification of a startup interlock circuit; several minor modifications to the control rod actuators; and the addition of the tube-sheet cooling system. (M.C.G.)</p>Army PWR Support and Development Program Six Months Summary Report : October 1, 1961 - March 31, 19622019-08-15T22:26:40-05:00https://digital.library.unt.edu/ark:/67531/metadc1201999/<p><a href="https://digital.library.unt.edu/ark:/67531/metadc1201999/"><img alt="Army PWR Support and Development Program Six Months Summary Report : October 1, 1961 - March 31, 1962" title="Army PWR Support and Development Program Six Months Summary Report : October 1, 1961 - March 31, 1962" src="https://digital.library.unt.edu/ark:/67531/metadc1201999/small/"/></a></p><p>Abstract: Progress is reported on research and development tasks under the Program Plan for Engineering Support and Development of Army Pressurized Water Reactor Power Plants, Contract AT(30-1)-2639, during the six months' period October 1, 1061 to March 31, 1962.</p>