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Control Concepts for Nuclear Ramjet Reactors

Description: Tory 11-A, the first experimental reactor in the Pluto nuclear ramjet program, will be tested in late 1960 at the Nevada Test Site of the Atomic Energy Commission. The fundamental objective of Tory II-A is to demonstrate that a high power density, high-temperature, air-cooled reactor can be successfully designed, constructed, and operated. This application places requirements on the reactor control system which are considerably more stringent than those found in previous reactor systems, both f… more
Date: June 11, 1960
Creator: Finnigan, Robert E.
Partner: UNT Libraries Government Documents Department
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The Interactions Of Strange Particles

Description: This report is a corrected copy of the authors "rapporteur talk" at the 1959 Kiev Conference on High Energy Physics. It contains data on the rapporteur system and on interactions of strange particles with protons and neutrons, using data from bubble chambers, counters, and emulsions.
Date: August 11, 1960
Creator: Alvarez, Luis W.
Partner: UNT Libraries Government Documents Department
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Diffusion of Fission Gases Through Uranium Oxide and Uranium Carbide

Description: A program has begun embodying a study of the diffusion rates of krypton and xenon into unirradiated UO2 and UC at temperatures between 1000°C and 2500°C.The experimental technique is described in some detail, involving exposure of UO2 and UC samples to a Kr85 atmosphere at various temperatures, removal of surface-adsorbed krypton, dissolution of the sample, collection and ion chamber measurement of the diffused Kr, and calculation of diffusion coefficients from these data.
Date: August 11, 1960
Creator: Weinstock, J. J.
Partner: UNT Libraries Government Documents Department
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Decoupling Concepts and Project Cowboy

Description: This paper for the Project Vela Technical Symposium is intended to be a brief resume of the principle results of the Cowboy program. The material is taken from a report entitled "Use of Large Cavities to Reduce Seismic Waves from Underground Explosions" by Herbat, Werth, and Spring (1960). As a result, no effect is made to justify each step in the analysis; reference should be made to the complete report.
Date: October 11, 1960
Creator: Werth, Glenn C.
Partner: UNT Libraries Government Documents Department
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Development of a Welding Process for Spire-Can Fuel Elements

Description: The components for the present aluminum clad, Al-Si bonded, internally and externally cooled (I & E), uranium fuel elements are composed of impact extruded cans and spire caps as shown in Figure 1. This type of component requires two impact extrusions; however, in December, 1957, J. E. Ruffin proposed another design of component in which there was only one impact extrusion. For this component, Figure 2, the spire was impact extruded as a part of the can.
Date: March 11, 1960
Creator: Hanson, G. R.
Partner: UNT Libraries Government Documents Department
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Zircaloy Process Tube Monitoring

Description: The large scale application of Zircaloy-2 pressure tubes for structural use either in or out of reactor service, is without precedent. For more common materials, there normally are adequate data and long operating histories on which to base design and service limits. In the absence of such information for Zr-2, several investigative programs have been devised to provide much of the information from which design and service limits may be defined for Zr-2 pressure tubes. These investigations enco… more
Date: April 11, 1960
Creator: Pankaskie, P. J.
Partner: UNT Libraries Government Documents Department
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Hydraulic System Flow Decay Relations During Loss of External Power

Description: Over the last decade, several computational methods have been developed and used to examine reactor flow transients caused by pump outage. The variations in system character which have been analyzed are sufficiently diverse that it appears worthwhile to compile them into a single report.
Date: February 11, 1960
Creator: Love, W. J.
Partner: UNT Libraries Government Documents Department
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Dry Maintenance Facility for the HRT

Description: A portable shield has been designed, developed, fabricated and shop tested to provide the HRT with a facility for direct dry maintenance operations. It provides temporary replacement for any one of the lower roof plugs and should permit many operations to be performed without flooding the reactor cell with water.
Date: October 11, 1960
Creator: Holz, P. P.
Partner: UNT Libraries Government Documents Department
open access

Local Reactivity "Worth" in the HRT

Description: The effect of adding small quantities of fuel or poison to the HRT has been estimated using perturbation theory. The results have been reduced to a single relation and a set of graphs which make the estimation of added reactivity relatively simple. The perturbation theory results are compared with multigroup results and reasonable agreement is demonstrated; however, there is some question concerning the prompt neutron lifetime.
Date: October 11, 1960
Creator: Jaye, S. & Vondy, D. R.
Partner: UNT Libraries Government Documents Department
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