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Design of production test IP-468-A-FP, program for evaluation of alpha extruded fuel cores

Description: The alpha phase extrusion of dingot bars to rods for core blank heat treatment at MCW offers a three-fold incentive, including: (1) establishment of an independent alternate source of uranium cores, (2) a slight cost improvement of MCW extrusion over FMPC rolling of dingot and (3) potential improvement in core quality and performance. The purpose of this test is two-fold: (1) to evaluate gross dimensional stability and (2) to evaluate the gross irradiation performance of alpha phase extruded di… more
Date: January 28, 1962
Creator: Clinton, M. A. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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BWR Reference Design for PL-3

Description: Abstract: The natural circulation, direct cycle, boiling water reactor reference design presented in this technical report is the alternate to the preferred preliminary design developed under Phase I of the PL-3 contract. The report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant eq… more
Date: February 28, 1962
Creator: Humphries, G. E.
Partner: UNT Libraries Government Documents Department
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Comparison of Gaseous Waste Handling Systems for PL-3

Description: Gaseous waste handling systems are compared for direct and indirect boiling water and pressurized water reactors for PL-3 application. Areas that are common to the various concepts are not discussed since they do not enter into a comparison study. The major differences present are in the handling of active gases released to or held in the primary system coolant. These gases which could be present, their possibIe release from the system, and the necessary processing requirements are discussed in… more
Date: February 28, 1962
Creator: Noble, J. H. & Duke, E. E.
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF FREEZE VALVE FOR USE IN THE MSRE

Description: Three types of frozen-seal valves'' were tested for possible use in the MSRE. The seal was melted by direct resistance heat, by induction heat, and by clamp-on Calrod heat. The frozen seal was made in a preformed restriction section of a standard piece of pipe by a cooling-gas jet stream directed at the restriction. All three valves performed satisfactorily through 100 test cycles. The Calrodheated valve was selected for MSRE use on the basis of simplicity of design and of operation. Two of the… more
Date: February 28, 1962
Creator: Richardson, M.
Partner: UNT Libraries Government Documents Department
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Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures.

Description: Abstract: Test procedures for special tests involving in-core SM-1 temperature and flow instrumentation are described (Task XIV Package Tests). These tests involve in-core steady state flow and temperature measurements, loss of flow transients, load transients, reduced primary system pressure operations and reduced element flow. The thermal and hydraulic conditions prevailing in these tests, including steady state and transient burnout rations, are developed. The effects of reduced system pres… more
Date: February 28, 1962
Creator: Bradley, P. L. & Coombe, J. R.
Partner: UNT Libraries Government Documents Department
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Improved Zirconium Alloys Annual Report: 1961 - 1961

Description: Annual technical report describing the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between February 1, 1961 to February 28, 1962 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: February 28, 1962
Creator: Weinstein, Daniel & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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PWR Preliminary Design for PL-3

Description: Abstract: The pressurized water reactor preliminary design presented in this volume is the preferred design developed under Phase I of the PL-3 contact. This technical report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant equipment, waste disposal, buildings and tunnels, services, … more
Date: February 28, 1962
Creator: Humphries, G. E.
Partner: UNT Libraries Government Documents Department
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Startup and Initial Testing of SM-1 Core II With Special Components

Description: The loading operation for SM-1 Core II is described. Results of startup physics measurements (Test A-300 (Series) and fission product iodine monitoring in the primary coolant are given. The SM-1 Core II initial loading progressed satisfactorily, fulfilling the predictions of the zero power experiment performed at the Alco Criticality Facility. The initial cold clean five rod bank position was 6.53 in.; the initial hot, no xenon, five rod bank position was 9.62 in.; the initial hot, equilibrium … more
Date: February 28, 1962
Creator: Moote, F. G. & Schrader, E. W.
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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Relocation of radial enrichment at the K reactors to decrease enrichment inventory

Description: The enrichment inventory required in the Hanford reactors is greatly dependent on the location of the radial enrichment ring. Present and past philosophy has dictated that the radial enrichment be located as close to the periphery of the reactors as possible, consistent with total control criteria, to obtain maximum flattening efficiency. As long as individual tube power limits dictate total pile power this philosophy of maximum flattening is consistent with a goal of maximum production. For th… more
Date: March 28, 1962
Creator: Kosmata, A. R.
Partner: UNT Libraries Government Documents Department
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Some Observations Regarding Rare-Earth Lactates

Description: From abstract: "Lactates of all the rare earths except lanthanum, cerium, and praseodymium were prepared and studied. In the case of lanthanum, cerium, and praseodymium the lactates are apparently so soluble that they cannot be crystallized directly from aqueous solution. Products obtained by addition of anhydrous ethanol to sirupy solutions of the light-rare-earth lactates were not well characterized and were deliquescent. Neodymium lactate trihydrate was prepared only by the addition of alcoh… more
Date: March 28, 1962
Creator: Powell, J. E. & Farrell, J. L.
Partner: UNT Libraries Government Documents Department
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SOME OBSERVATIONS REGARDING RARE-EARTH LACTATES

Description: Lactates of all the rare earths except lanthanum, cerium, and praseodymium were prepared and studied. In the case of lanthanum, cerium, and praseodymium the laciates are apparently so soluble that they cannot be crystallized directly from aqueous solution. Products obtained by addition of anhydrous ethanol to sirupy solutions of the iight-rare-earth lactates were not well characterized and were deliquescent. Neodymium lactate trinydrate was prepared only by the addition of alcohol to a sirupy s… more
Date: March 28, 1962
Creator: Powell, J.E. & Farrell, J.L.
Partner: UNT Libraries Government Documents Department
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Tory II-C performance parameters

Description: Declassified 27 Nov 1973.<><DSN>29:020169<ABS>Declassified 27 Nov 1973.
Date: March 28, 1962
Creator: Var, R.; Uthe, P.M. & Mintz, M.
Partner: UNT Libraries Government Documents Department
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Carbide Fuel Development. Progress Report, January 1, 1962 to March 31, 1962

Description: Reproducibly high density UC-PuC pellets containing minor amounts of (U,Pu)/sub 2/C/sub 3/ were made with nickel sintering aid. Average densities of 95% and maximum densities of 96.6% of theoretical were obtained. High density, singlephase UC-PuC pellets were made by sintering at high temperatures. Densities of 94% of theoretical appear to be attainable. Improved identification of microstructural constituents was made by means of metallography, x-ray diffraction, and microprobe analysis. Develo… more
Date: May 28, 1962
Creator: Strasser, A. & Taylor, K.
Partner: UNT Libraries Government Documents Department
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Electron Requirements of Bonds in Metal Borides

Description: From abstract: "Electrical measurements have been made on CaB6, SrB6, BaB6, YB2, YB4, YB6, and YB12 for the purpose of testing models of the electronic structure of the boron atoms in the four boride types represented. The compounds CaB6, SrB6, and BaB6 were found to be semiconductors. The Hall coefficients of YB4 was also measured, but could not be interpreted because the free electron theory does not provide a theoretical value for comparison with experiment. The results are in agreement with… more
Date: May 28, 1962
Creator: Johnson, Robert W. & Daane, A. H. (Adrian Hill), 1919-
Partner: UNT Libraries Government Documents Department
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Production test IP-508-D irradiation of a porous stainless steel clad fuel element assembly

Description: A large number of irradiation tests have been conducted with UO{sub 2} fuel elements to characterize the behavior of Zircaloy cladding when cooling water is allowed to penetrate the cladding to the fuel core. The test element, is designed so that cooling water will be in contact with the surface of the UO{sub 2} fuel core during irradiation. The irradiation behavior of the UO{sub 2} will be compared to the behavior of similarly irradiated, non-defected UO{sub 2} fuel-elements. Several character… more
Date: May 28, 1962
Creator: Marshall, R. K. & Cox, J. H.
Partner: UNT Libraries Government Documents Department
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Response of Protective Vaults to Blast Loading

Description: A reinforced-concrete steel-plate-lined vault and steel vault door were exposed to a nuclear detonation (shot Priscilla, about 37 kt, balloon suspended, at 700 ft) at the predicted 75-psi peak incident pressure level (1150 ft from Ground Zero). The vault was designed by the ultimate-strength theory to utilize the additional strain energy available in the elastoplastic and plastic ranges. Flexural and thrust capacities were determined, and shear capacity was computed. It was established that abo… more
Date: May 28, 1962
Creator: Cohen, Edward; Laing, E. & Bottenhofer, A.
Partner: UNT Libraries Government Documents Department
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Storm Data and Unusual Weather Phenomena, Volume 4, Number 4, April 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: May 28, 1962
Creator: United States. Weather Bureau.
Partner: UNT Libraries Government Documents Department
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