Technical Report Archive & Image Library (TRAIL) - 35 Matching Results

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A Summary of the Ground-Water Hydrology of the Area Between the Las Vegas Valley and the Amargosa Desert, Nevada: with Special Reference to the Effects of Possible New Withdrawals of Ground Water

Description: Introduction: The United States Atomic Energy Commission is considering the establishment of a townsite in the vicinity of Mercury, Nevada, to facilitate operations at the Nuclear Rocket Development Station on the Nevada Test Site.
Date: September 1963
Creator: Winograd, Isaac Judah
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Facility for the Production of Pu238

Description: Abstract: A pilot plant facility for recovering Pu238 and unconverted neptunium from irradiated neptunium target elements was operated for 17 months at the Savannah River Laboratory. The process required that the irradiated target elements be dissolved and the solution be processed through three anion exchange cycles for removal of undesirable fission products and cations, recovery of unconverted neptunium, and concentration of Pu238 solution. The process equipment was enclosed in three stain… more
Date: September 1963
Creator: Tetzlaff, R. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Geologic and Seismic Investigations of Proposed Nuclear Power Plant Site on Bodega Head, Sonoma County, California

Description: The following report covers the study of the site adjacent to Campbell Cove on Bodega Head, Sonoma County, California, focusing on questions such as: 1) its position relative to the San Andreas fault zone; 2) the possibility that minor faults, related to the San Andreas fault, might actually pass through the site; and 3) the seismic hazards posed by the nearby San Andreas fault zone.
Date: September 1963
Creator: Eaton, Jerry P.; Schlocker, Julius; Bonilla, Manuel G. & Clebsch, Alfred, Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Stratospheric Monitoring Program

Description: "The performance of the Model I electrostatic precipitator sampler in recent field and laboratory tests is described and discussed. Two of the four precipitator-bearing balloon flights during this interval reached the floating altitude of approximates 105,000 feet, and the precipitator operated efficiently on both. One sample was collected at the nominal design flowrate of approximates 100 cfm, and the second at approximates -200 cfm. Comparison of the deposition profiles of the stratospheric s… more
Date: September 18, 1963
Creator: Cravitt, S.; Lippmann, M.; Lilienfeld, P. & Viggiano, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Basis for the Computation of the Energy Dependence of the Neutron Flux and Slowing Down Density in a Bare Reactor

Description: A method is described for the computation of the energy dependence of the neutron flux and slowing down density in a bare reactor to form the basis of a 7090 Fortran computer program for survey studies of power reactors. Allowance is made for resonance absorption and resonance fission, neutron thermalisation, fast neutron reactions including (n, 2n) and (n, n), and anisotropic elastic scattering.
Date: September 1963
Creator: Lawrence, B. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Procedures and Equipment Used in Inhalation Studies on Small Animals

Description: From Introduction: "These facts prompted the initiation of an effort to develop appropriate exposure equipment. The purpose of this communication is first, to describe an apparatus which, with modifications, allows pertinent information to be obtained on each individual small animal exposed and secondly, to set forth the pre- and post-exposure procedure adopted for obtaining required quantitative data regarding respiration, deposition. distribution and excretion."
Date: September 1963
Creator: Thomas, R. G. & Lie, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Measurement of Fission Gas Pressure in Operating Fuel Elements: Post-Irradiation Examination

Description: Summary: Two UO2-filled stainless steel clad fuel rods in which fission gas pressure was measured during irradiation have been subjected to post irradiation examination. Results of free gas analysis and metallographic examination are in general agreement with observed pressures reported previously. Calculated fuel surface temperatures based on extent of fuel recrystallization indicate that in a one-half inch diameter fuel rod with 0.014 inch diametral clearance operated at a maximum heat flux o… more
Date: September 20, 1963
Creator: Reynolds, M. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Multirod (Four Rod) Critical Heat Flux at 1000 PSIA

Description: Technical report describing the four-rod heat flux experiments that are a part of a continuing program of study of the critical heat flux, or burnout phenomenon in order that water cooled reactors can be designed with a maximum of safety and efficiency. During heat transfer with boiling, there is a particular heat flux, for a given set of flow conditions and geometry, above which the nucleate boiling process begins to break down. This breakdown of the nucleate boiling process is known as burno… more
Date: September 1963
Creator: Hench, John E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Failure Examinations and Analyses in the High Power Density Program

Description: Summary: The High Power Density Project includes a comprehensive fuel development program which has the objective of developing and demonstrating the performance of a nuclear reactor core having a high power density, long fuel life, and low fabrication cost. The fuel program is made up of two principal tasks. Task 1A consists of irradiation tests in the VBWR of Type 304 stainless steel clad, UO2 pellet type fuel rods fabricated by current commercial processes. Task 1B consists of the investigat… more
Date: September 16, 1963
Creator: Arlt, W. H. & Vandenberg, S. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Two-Phase Pressure Losses Quarterly Progress Report: Sixth Quarter, May 12, 1963 - August 12, 1963

Description: Technical report describing that the pressure drops along 3/4-inch, 1-inch, and 1-1/4 inch straight pipes and across three contraction-expansion inserts in a 1-inch pipe have been measured under both single- and two-phase flow conditions. Pressure was varied from 600 to 1400 psia, flow from 0.25 x 10(6) to 1.66 x 10(6) lb/hr ft, and quality from zero to 90 percent. The single-phase pipe friction factor agrees with the Moody value for smooth pipe. The two-phase friction for horizontal flow shows… more
Date: September 1, 1963
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Program of Two-Phase Flow Investigation Quarterly Report: Second Quarterly Report, July-September, 1963

Description: Task A: Modification and Preparation of Experimental Facility. With the exception of the insulation of modified components, the experimental facility is complete. Insulation will be completed by the end of September. the system has been charged with Refrigerant-22 and preliminary loop performance tests have been completed without the test sections.. Task B: Design and Construction of Test Sections. The stainless steel test section has been prepared complete with end flanges and pressure tap loc… more
Date: September 23, 1963
Creator: Staub, F. W. & Zuber, N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Operational Physics Data from the HWCTR

Description: The Heavy Water Components Test Reactor (HWCTR) was built for the Atomic Energy Commission by the Du Pont Company to satisfy a need for fuel testing in the AEC's Heavy Water Power Reactor Program. The reactor was designed to provide a realistic test environment for full size fuel candidates. The report contains sections on (1) the containment building, (2) vertical cross section of the reactor vessel, (3) core layout, (4) low power physics tests and comparison with calculations, (5) rod worth… more
Date: September 20, 1963
Creator: Rusche, Benard Clements, 1931-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Failure Detection in the Heavy Water Components Test Reactor

Description: The Heavy Water Components Test Reactor (HWCTR) is a pressurized reactor, cooled and moderated with D2O, and has the capability of testing fuel assemblies under operating conditions of coolant flow, temperate, and pressure that are typical of those proposed for modern power reactors. The report contains (1) description of the four systems used for failed element detection, (2) discussion of the laboratory analyses of water samples used a as backup for the fuel failure instruments, (3) descript… more
Date: September 20, 1963
Creator: Kiger, E. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Control of the Dissolved Gases in the Moderator of the HWCTR

Description: The Heavy Water Components Test Reactor (HWCTR) is used to test prototype fuel elements for power reactors that are moderated with heavy water and fueled with natural or slightly enriched uranium. During the initial critical experiments in the HWCTR, it was observed that there were unexpected variations in nuclear reactivity. Investigations revealed that this effect was due to bubble of helium gas appearing and disappearing in the moderator. An examination of the expected operating conditions… more
Date: September 20, 1963
Creator: Arnett, L. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Staffing Experience for Operation of the Plutonium Recycle Test Reactor

Description: The Plutonium Recycle Test Reactor is a research and development tool supporting the Plutonium Recycle Program and the research activities at Hanford. The present organization directly associated with the PRTR is composed of Operating, Technical Assistance, Maintenance, and Engineering Groups. Liaison with research groups utilizing PRTR facilities is accomplished through the Technical Assistance Group. the other three groups serve the PRTR in the manner suggest by the group name. This paper … more
Date: September 23, 1963
Creator: Koberg, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Usefulness of the Kangaroo Rat

Description: Abstract. The kangaroo rat is readily tamed and has certain characteristics that make it unique and of interest in highly specialized research programs. Studies were conducted on its ability to exist on a dried diet with only a bare minimum of water and that obtained from succulent plants. Hematological studies indicate that the kangaroo rat exhibits a different hematological distribution of cells than the mouse or rat. The lymphocyte constitutes 81.4% of the total leuokocytes. The hematocrit h… more
Date: September 13, 1963
Creator: Haley, Thomas J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Computer Information Center

Description: The purpose of the Computer Information Center is to stimulate the production of documentation and to make it readily available to computer users within the Laboratory. In addition, the Center will endeavor to obtain all publications of programming and machine manuals pertinent to LRL.For the Computer Information Center to be effective, it is essential that its coverage be as complete as possible. Computer users who have written programs or subroutines are therefore urged to submit write-ups fo… more
Date: September 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Research on Vapor Reheat And Liquid-Liquid Heat Exchange

Description: From Forward and From Introductory- Summary : "This is the seventy-eighth of a series of reports designed to present accounts of progress in saline water conversion with the expectation that the exchange of such data will contribute to the long-range development of economical processes applicable to large-scale, low-cost dimineralization of sea or other saline water. The distillation system has operated with only minor difficulties. Mass transfer coefficients are in the range predicted from pr… more
Date: September 1963
Creator: FMC Corporation
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Absorption-Multistage Flash Distillation Process

Description: "The major factors which influence the cost of water production from sea water by distillation methods are (1) the cost of fuel or energy required by the distilling plant, and (2) the required capital investment. Preliminary studies on the application of absorption or solution cycles to distillation methods for saline water conversion indicated that the fuel cost or thermal economy of a distillation plant could be improved by combining the distillation process with an absorption or solution cyc… more
Date: September 1963
Creator: Fluor-Singmaster & Breyer, Inc.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Breeding-Gain Specimens for EBR-I Core IV

Description: Report issued by the Argonne National Laboratory over studies conducted on uranium and plutonium specimens used in fuel rods. The results are presented and discussed. This report includes tables, illustrations, and photographs.
Date: September 1963
Creator: Shuck, A. B.; Hins, A. G.; Burt, W. R. & Beatty, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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