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Fast Neutron Flux Measurements and Analysis in SM-1 and PM-2A Core and Vessel Mockups

Description: Abstract: This technical report contains a summary of experimental and analytical work performed on cold clean SM-1 Core II with special components and PM-2A Core I each with thermal shield and vessel mockups. The purpose of this work was to define the neutron intensity and spectra to which the pressure vessels are subjected in order to assess the effect of irradiation on the vessel lifetimes. The radial distributions of the energy dependent neutron flux per unit power in the core and vessel m… more
Date: March 31, 1962
Creator: Sontheimer, K. C.; Kemp, S. N.; Lois, L.; Clancy, E. F. & McCool, W. J.
Partner: UNT Libraries Government Documents Department
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Preliminary Stress and Fatigue Analysis of the SM-1 Primary System

Description: A preliminary analysis of the SM-1 primary system showed it-was safe from strain cycling damage with the possible exception of steam generator tube sheet and primary pump casing. These are recommended for further analysis. (auth)
Date: March 31, 1962
Creator: Chittum, R. A.; Knipe, R. K. & McLaughlin, D. W.
Partner: UNT Libraries Government Documents Department
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Research in Radiobiology. Annual Report of Work in Progress on the Chronic Toxicity Program

Description: Separate abstracts were prepared on 8 sections of this report. Data are also included on the status of dogs at various time intervals following the injection of various doses of Ra/sup 226/, Pu/sup 239/, Ra/sup 228/, Th/sup 228, and Sr/sup 90/. (C. H.)
Date: March 31, 1962
Creator: Dougherty, T. F.
Partner: UNT Libraries Government Documents Department
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Startup Testing of the PM-2A Nuclear Power Plant

Description: Abstract: A detailed description of the PM-2A reactor, primary system and instrumentation is presented. A general description of the secondary system and plant arrangement at Camp Century, Greenland is included. The results of the startup physics, shielding, thermal and hydraulics and radiochemistry test are presented. the analysis performed on the shielding and thermal and hydraulic tests is included. The shielding problem at startup and the shielding modification made to the plant are describ… more
Date: March 31, 1962
Creator: McCool, W. J.; Ryan, R. M.; Richards, W. M. S.; Bradley, P. L.; Stephenson, L. D. & Cox, J. F.
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium. Quarterly Report No. 2, December 15, 1961 to March 14, 1962

Description: The purpose of this investigation is to determine the extent to which Zr and Zr alloys exhibit delayed failure (static fatigune) as caused by a combination of absorbed H and applied stress. Both notched and unnotched specimens of unalloyed Zr and Zircaloy-2 were hydrogenated to 200 ppm and 500 ppm by means of a modified Sieverts apparatus; specimens were evaluated at room temperature. Thus far, no time-dependent fracture was observed which can be attributed to the delayed failure phenomenon; it… more
Date: March 30, 1962
Creator: Weinstein, D. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium: Quarterly Report Number 2, December 1961 - March 1962

Description: Abstract: "The purpose of this investigation is to determine the extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress. Both notched and unnotched specimens of unalloyed zirconium and Zircaloy-2 have been hydrogenated to 200 ppm by means of a modified Sieverts apparatus; specimens were evaluated at room temperature. Thus far, no time-dependent fracture has been observed which can be attributed t… more
Date: March 30, 1962
Creator: Weinstein, Daniel & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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General Chemistry Technical Note No. 71: Hydrogen compounds of low atomic weight

Description: This report provides a compilation of Hydrogen compounds of low atomic weight. Compounds known and reported in literature are given. Cations and anions of high Hydrogen content and/or low Z are provided as are molecules which form Lewis salts. Finally, unknown compounds for which synthesis seems probable are given.
Date: March 30, 1962
Creator: Pearson, R. K.
Partner: UNT Libraries Government Documents Department
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Mound Laboratory Monthly Progress Report for March 1962

Description: In research on plastics, flow curve data were obtained on asbestos- filled diallyl phthalate formulations. The tensile properties of adhesive formulations after 26 weeks cure time are being tested. In development of radioelements, progress is reported in investigations of kinetics invoived in Po(IV) reduction by ferrous iron and selective adsorption of trace elements. Development of separating and purifying processes is reported for Xe, H/sub 2/, and C. Work on the Ranger x-ray sensor was devot… more
Date: March 30, 1962
Creator: Eichelberger, J. F.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Meeting: March 1962

Description: A report regarding proceedings of the nuclear superheat meeting no. 6, held March 7, 8 and 9, 1962, in Windsor, Connecticut.
Date: March 30, 1962
Creator: Mravca, Andrew E.
Partner: UNT Libraries Government Documents Department
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PM-2A Core II Zero Power Experiment

Description: Abstract: This technical report covers the zero power experiments performed on PM-2A Core II at the Alco Critical Facility. PM-2A Core II is the first replacement core for a portable pressurized reactor at Camp Century, Greenland. Core II is the same as Core I with the exception that Core II has an increased burnable poison (B-10) content. The zero power experiment consisted of fuel element uniformity test; core assembly test, development of an on-site loading procedure and an analysis of exper… more
Date: March 30, 1962
Creator: Walthousen, L. D.; Mageean, J. V.; Raby, T. M. & Lee, D. H.
Partner: UNT Libraries Government Documents Department
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Preliminary Technical Report SM-1 Core III with Type 3 Elements

Description: Abstract: This preliminary technical report covers design of the SM Type 3 element, its use .in.. SM-1 Core III, and planned use in the Type 3 Core for PM-2A. The Type:3 element characteristics are compared with Type 1 (SM-1 Core I) element nuclear, metallurgical, thermal and hydraulic characteristics and fabrication. The effect of using the Type 3 element in SM-1 Core III and. its planned use in a Type 3 Core for PM-2A is discussed with regard to operation, shielding, reactor safety and all co… more
Date: March 30, 1962
Creator: Inglima, J. N.; Beam, R. H.; Davidson, S. L. & Edgar, E. C.
Partner: UNT Libraries Government Documents Department
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Storm Data and Unusual Weather Phenomena, Volume 4, Number 2, February 1962

Description: Monthly report containing a chronological listing, by state, of hurricanes, tornadoes, thunderstorms, hail, floods, drought conditions, lightning, high winds, snow, temperature extremes and other weather phenomena. It also provides information on storm paths, deaths, injuries, and property damage.
Date: March 30, 1962
Creator: United States. Weather Bureau.
Partner: UNT Libraries Government Documents Department
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Stress Analysis of the SM-1A Reactor Vessel

Description: The stress analysis performed on the SM-lA reactor vessel and cover is presented. The msximum combined stress (51,360 psi in compression) occurs in the vessel cover during a 50 deg F/hr transient. A fatigue analysis of these stresses indicated that they could be applied safely at least 2500 times, and since the vessel is expected to receive less than 900 cycles, it should not suffer any fatigue damage. (auth)
Date: March 30, 1962
Creator: McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A. & Aitken, C. C.
Partner: UNT Libraries Government Documents Department
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Summary Report of Analysis of Physics Measurements Performed on SM-1 Core I

Description: Abstract: This technical report contains a comprehensive analysis of the nuclear characteristics of the SM-1 Core I. Comparison of analytical and experimental results for neutron ages and core reactivities of a variety of cases investigated shows that the MUFT III with P-1 slowing down approximation gives the best results. At startup the core reactivity and rod bank worth under various operating conditions are investigated and compared to experiment. Core lifetime was calculated to be 16.8 MWYR… more
Date: March 30, 1962
Creator: Lois, L.; Paluszkiewicz, S.; Fried, B. E. & Beam, R. H.
Partner: UNT Libraries Government Documents Department
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SYNTHESES OF SOME ALKALI-METAL p-ETHYLBENZENESULFONATES

Description: Methods were developed for the syntheses of alkalimetal p--bar ethylbenzenesulfonates. P--bar ethylbenzenesulfonic acid is isolated and is purified as barium p--bar -ethylbenzenesulfonate which is converted to the Na, K, or Cs p-bar -ethylbenzenesulfonate by means of a slight excess of the corresponding alkali-metal carbonate. Lithium sulfate is used to form the lithium p-bar -ethylbenzenesulfonate. (auth)
Date: March 30, 1962
Creator: White, J.C. & Holsopple, H.L.
Partner: UNT Libraries Government Documents Department
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Thermal Analysis of Type 3 Elements in the SM-1, SM-1A and PM-2A Cores

Description: Report describing a study which analyzed thermal characteristics of Type 3 elements planned for installation in the SM-1, SM-1A and PM-2A plants, for both steady state and loss of flow transient conditions. Results of this analysis for steady state conditions indicate that the SM-1, SM-1A and PM-2A Type 3 cores will operate safely at design and scram conditions.
Date: March 30, 1962
Creator: Davidson, S. L. & Segalman, I.
Partner: UNT Libraries Government Documents Department
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Thermoelectric Nuclear Fuel Element. Addendum to Final Report

Description: A twenty-couple fission-heated thermoelectric generator, TE-5, was tested in the Westinghouse Testing Reactor. The open circuit voltage, instantaneous closed circuit voltage, steady state closed circuit voltage, instantaneous closed circuit current, and steady state closed circuit current were monitored during the 23-day cycle. The initial power output was 110 watts (48 amps at 2.3 volts) at a TH of 660 to 690 deg C and a T/sup C/ of 130 deg C. After 23 days the output was approximately one wat… more
Date: March 30, 1962
Creator: Danko, J. C.
Partner: UNT Libraries Government Documents Department
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Heating in the shield

Description: No Description Available.
Date: March 29, 1962
Creator: Clement, J.D.
Partner: UNT Libraries Government Documents Department
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Instrumentation studies, Status report

Description: Two computer codes (1- and 6-node models) were used in the calculations. For the 1-node model, standard reactor kinetics,heat transfer, and instrument delay equations were programmed for analog and digital computers; effects of full-pile reactivity insertions were calculated. The 6-node model contains the time-dependent diffusion equations and heat transfer and instrument delay equations; it was programmed for the analog computer only, and was used to calculate effects of local reactivity inser… more
Date: March 29, 1962
Creator: Stiede, W. L. & Monnie, D. I.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Technology Quarterly Progress Report, October-December 1961

Description: The ICPP processed Al fuel, prtncipally of the MTR-ETR type, durtng this quarter. Newly designed and installed processing equipment exhibited excellent operating performance. This included direct-air-pulsed extraction, stripping and scrub columns, and a cascade-controlled continuous evaporator in first cycle product concentration service. Aqueous zirconium fuel processing studies continued with the objective of adapting the hydrofluoric acid process to continuous dissolution-complexing to incre… more
Date: March 28, 1962
Creator: Bower, J. R.
Partner: UNT Libraries Government Documents Department
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