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Aerial Radiological Monitoring System: Part 2. Performance, Calibration, and Operational Check-Out of the EG&G ARMS-II Revised System

Description: Report describing "the design, installation, and performance of the Edgerton, Germeshausen & Grier, Inc., Aerial Radiological Monitoring System used in Phase II of the Aerial Radiological Monitoring Survey (ARMS-II)" (p. 5). Contains descriptions and photographs of its components and descriptions of test runs.
Date: October 1961
Creator: Hand, J. E.; Guillou, R. B. & Borella, H. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aerial Radiological Monitoring System: Part 3. Electronic Processing of ARMS-II Data

Description: Report detailing the instrumentation and system performance of the Aerial Radiological Monitoring Survey (ARMS-II), a system used "to perform aerial surveys of ground radioactivity. It supplies both geographical position and radioactivity data in digital form, suitable for use with automatic plotting procedures" (p. 5)
Date: October 1961
Creator: Hand, J. E. & Borella, H. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Analysis of Specific Heat Data for Water and Water Vapor in the Critical Region. Technical Report No. 8

Description: A comprehensive review of the available data for the specific heat at constant pressure of water and water vapor is given for pressures from 14.22 to 4300 psia and temperatures from 680 to 800 deg F. ln addition a description is given of the various experimental techniques employed by different investigators to carry out measurements of this property. Deviations of up to 20% are shown to be in existence between the measured values of specific heat of different investigators. The estimated appar… more
Date: October 1, 1961
Creator: Nowak, E. S. & Grosh, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Argonne National Laboratory Chemical Engineering Division Summary Report: July, August, September 1960

Description: 9 : : 7 : 7 9 : 5 5 ? 5 9 G -- 8 ; 8 ; = -activity levels of the melt-refining process for EBR-II core fuel was completed. An experiment was also completed on the evolution of fission- product krypton and xenon from an irradiated fuel pim as it was heat to a temperature above the melting point. In tests of alternate materials for use in a meltrefining furnace, a fibrous potassium titanate grain retainer was found to be a very effective heat insulator, but to have less strength than nigid Fibenf… more
Date: October 1961
Creator: Argonne National Laboratory. Chemical Engineering Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Argonne National Laboratory Physics Division Summary Report: September, October 1960

Description: The use and operation of the Van de Graaff generator are summarized for the period from January 1 to June 30, 1960. Molecular beam study final results are given for Mn/sup 56/, and progress on the new atomic-beam machine is reported to date. A preliminary investigation was made of the neutron total cross section of cobalt. Results are presented. The decomposition of trichlorobromomethane by the isomeric transition of 4.4-hr Br/sup 80m/ and to 1000 deg F. /sup -/, decay of 35.9-hr Br/sup 82/ was… more
Date: October 1961
Creator: Argonne National Laboratory. Physics Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report, April, May, June 1961

Description: Developments in chemical engineering are described. Pyrometallurgical development, fuel-processing facilities for EBR-II, pyrometallurgical research, laboratory and engineering-scale investigations of fluoride volatility processes, conversion of UF/sup 6/ to UO/sup 2/, calcination studies in small-diamenter columns, metal oxidation and ignition kinetics, metal-water reactions, determination of nuclear constants, thermally regenerative emf cell, thermoelectricity research, reactor decontaminatio… more
Date: October 1, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cockpit Control-Display Subsystem Engineering

Description: Reporting presenting cockpit control-display subsystems schedules as a sequence of design activities. The relationships between activities within control-display design and the rest of the system are shown.
Date: October 1961
Creator: Kearns, John K. & Ritchie, Malcolm L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Conceptual Design of a 300-Mwe Paste-Fueled Fast Breeder Power Reactor

Description: "This report describes the conceptual design of 300 Mwe fast breeder reactor power plant that utilizes a paste-fuel system consisting of small, spherical particles settled in sodium" (p. 7). It includes a discussion of the paste-fuel system, the design of the core and blanket structure with analysis, a description of the fuel-handling system, processes for fabricating and processing the fuel, and schematics.
Date: October 1961
Creator: Blessing, W. G.; Bowers, S. D.; Hennig, R. J.; Huebotter, P. R.; Jens, W. H.; Kovacic, E. C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE CONTINUOUS MONITORING OF BORIC ACID CONCENTRATION BY NEUTRON ABSORPTIOMETRY

Description: A neutron absorption cell was built to monttor continuously the boric actd concentration of reactor water flowing through a purtfication loop. The instrument was calibrated over the range from 0 to 2.65 g/l with a maxtmum absolute error of 0.05 g/-l. (auth)
Date: October 1, 1961
Creator: Armani, R.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CRITICAL STUDIES OF A DILUTE FAST REACTOR CORE (ZPR-III ASSEMBLY 31)

Description: Critical studies were performed on a dilute, metallic, fast reactor core. The fuel was 38.6% enriched uranium and reduced-density aluminum was used to simulate sodium coolant. The measured critical mass was 463 kg of U/sup 235/ in a 425-liter core. The main part of the experimental program consisted of measurements of the standard fission ratios, a number of central reactivity coefficients, and the prompt neutron lifetime. An additional series of experiments were performed to obtain the worths … more
Date: October 1, 1961
Creator: Gasidlo, J. M.; Long, J. K. & McVean, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DESIGN AND REVIEW OF STRUCTURES FOR PROTECTION FROM FALLOUT GAMMA RADIATION

Description: The formation, distribution, and biological effects of fallout are reviewed. Design features of structures for protection against fallout gamma radiation are described. Factors affecting gamma dose rate, shielding geometry, special shielding problems, and ventilation in shelters are discussed. Calculations are presented of the gamma dose from fallout for simple underground shelters, simple aboveground shelters, basement shelters, upper-story shelters, and compartmentalized structures. Charts fo… more
Date: October 1, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF CENTRIFUGAL COMPRESSORS

Description: Coolant flow for gas-cooled in-pile loops must be supplied during irradiation test runs. A centrifugal compressor has been designed and developed for circulating helium at volume flows from 75 to 250 acfm at compressor suction conditions of 400 psi and 600 deg F. The compressor using grease-lubricated ball bearings has operated satnksfactorily for a total of 3500 hr. (auth)
Date: October 1, 1961
Creator: Namba, I.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Economic Analysis of Replacement Cores for SM and PM Type Reactors

Description: An economic analysis is presented for the fabrication of replacement cores for SM and PM type reactors, including analysis of various core types and core fabrication technologies. The analysis indicates that major savings are possible by utilizing Type 3 cores (40-mil plates, 25 wt% UO/sub 2/, welded assembly) in all SM and PM type reactors, and that significant savings are possible by multiple core procurement and reprocessing, and relaxation of cobalt and tantalum requirements in Type 347 sta… more
Date: October 1, 1961
Creator: Wilder, A. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE EFFECT OF MANGANESE AND SILICON CONTENT ON THE HOT WORKABILITY OF TYPE 304 STAINLESS STEEL CONTAINING 2 w/o BORON

Description: Increased hot workability of Type 304 stainless steel containing approximately 2 wt% boron was obtained by maintaining the manganese and silicon contents of the alloy above minimum levels of 1.40 and 0.60 wt%, respectively. Close control of the range of temperatures over which hot working was carried out was also demonstrated to be of importance. However, over the range investigated variation in the temperature of hot working was of secondary significance as compared with alloy composition. (au… more
Date: October 1, 1961
Creator: Hymes, L. C. & Balai, N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Electrical Measurements on the Growing Scale on Zirconium-Titanium Alloys

Description: The corrosion rates of low-titanium zirconium alloys increased with titanmum content when exposed to water at 290 deg C or to 1 atm oxygen at 290, 350, 400, and 500 deg C. The scaling rate reached a maxmmum (approximately 3000 at 500 deg C and then decreased with increasing titanium content. Under the same conditions, pure zirconium and tmtanium had much lower weight gains, 10 and 4 mg/ dm/sup 2/ respectively. In oxygen at 500 deg C, the oxidation rate law was initially cubic or parabolic for a… more
Date: October 1, 1961
Creator: Misch, R. D. & Iseler, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electrolytic Dissolution of Power Reactor Fuels in Nitric Acid

Description: The electrolytic oxidation in nitric acid of stainless steel, zirconium, Zircaloy-2, zirconium- uranium alloy, aluminum, and uranium - molybdenum alloy was demonstrated on a laboratory scale. The rate of chemical dissolution of UO/ sub 2/ in nitric acid was measured. Corrosion of stainless steel by these dissolver solutions was measured and found to be negligible. Electrolytic dissolution was demonstrated to be a practical technique for the first step in processing fuel elements of several type… more
Date: October 1, 1961
Creator: Clark, A. T., Jr.; Meyer, L. H.; Owen, J. H. & Rust, F. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Engineering Capabilities of in-Pile Irradiation Facilities Used by GE-ANPD

Description: GE-ANPD had exclusive use of irradiation testing facilities in four reactors: the Materials Test Reactor (MTR), the Engineering Test Reactor (ETR), the Low lntensity Test Reactor (LlTR), and the Oak Ridge Research Reactor (ORR). A compilation of data concerning the GE-ANPD facilities in these reactors is presented. lnstrumentation capabilities, dimensions of the in-pile tubes, flow characteristics, control capabilities, and detailed design data are listed. (auth)
Date: October 1, 1961
Creator: Harry, R. J. & Fries, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of a Thin-Film Sea Water Distillation Unit for Marine and Shore Base Application

Description: Report issued by the Office of Saline Water over studies conducted on a thin film sea water distillation unit. As stated in the summary, "a General Electric Thin Film Sea Water Distillation Unit designed for marine application has been evaluated. The results demonstrate the feasibility of the thin film process for this application. The technology made available by this work provides criteria for the design of compact equipment" (p. 1). This report includes tables, illustrations, and photographs. more
Date: October 1961
Creator: General Electric Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Evaluation of Reactor Concepts for Use as Separate Steam Superheaters

Description: Various reactor concepts were compared for use as a separate superheater which could be added on to an advanced 300-Mwe reactor producing saturated steam. Fossil steam plant superheat temperatures were used as a criterion for selecting nuclear superheat temperatures. Therefore, the performance specified for the superheater was a minimum exit steam temperature of 566 deg C (1050 deg F) when supplied with saturated steam at either 7l atm (l050 psia) or l67 atm (2450 psia). A preliminary screening… more
Date: October 1, 1961
Creator: Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

Figure 2.3: Arms-II Computer-Program and Data-Processing Monitor

Description: Flowchart outlining the event sequencing in the "MAIN" program (primary body of operational instructions which accepts data, routines data to sequential manipulations, prints data, etc.) within the Aerial Radiological Monitoring Survey (ARMS-II) system. The ARMS-II system is used "to perform aerial surveys of ground radioactivity. It supplies both geographical position and radioactivity data in digital form, suitable for use with automatic plotting procedures" (p. 5, report)
Date: October 1961
Creator: Hand, J. E. & Borella, H. M.
Item Type: Refine your search to only Technical Drawing
Partner: UNT Libraries Government Documents Department
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