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open access

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.
open access

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.
open access

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.
open access

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.
open access

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.
open access

Effective Cadmium Cutoff Energies

Description: Effective cutoff energies for point l/v absorbers inside of spherical and cylindrical cadmium filters have been calculated for thermal reactor neutrons. The neutron spectrum was assumed to consist of a Maxwellian plus a 1/E component, and the parameters varied were the thickness of filter, the Maxwellian temperature and the Maxwellian to 1/E flux ratio. Because of the sensitivity of the effective cutoff to Maxwellian flux parameters for thin filters it is recommended that filter thicknesses of … more
Date: March 11, 1960
Creator: Stoughton, R.W.; Halperin, J. & Lietzke, M.P.
open access

ELECTRON-SPIN-RESONANCE STUDIES ON PHOTO-SYNTHETIC MATERIALS

Description: A number of organisms have been examined for their ability to produce electron-spin-resonance signals at low temperatures in response to illumination. The efficiency of the response is of the order of not less than 5%, and the wavelength for maximum response is generally slightly on the longer side of the wavelength of maximum absorption, with a minimum appearing at the wavelength of maximum absorption.
Date: May 11, 1960
Creator: Sogo, Power B.; Carter, Louise A. & Calvin, Melvin.
open access

Experience with anthracite - sand filters

Description: The General Electric Company operates eight large filter plants for the Atomic Energy Commission at the Hanford works in the state of Washington. Because of the importance of water to the process, research and development on water treatment has been an important part of the overall Hanford research and development program. The research and development on water treatment has resulted in important capital and operating savings and in the production of better quality water. It is the purpose of th… more
Date: November 11, 1960
Creator: Conley, W.R.
open access

Further Development of Gas-Pressure Bonding of Zircaloy-Clad Flat-Plate Uranium Dioxide Fuel Elements

Description: The effects of core barrier coatings, void spaces, and surface-cleaning techniques on the quality of Zircaloyclad flat-plate UO/sub 2/ fuel elements prepared by gas-pressure bonding were investigated. Techniques were developed for the application of barrier layers of chromium by a vapordeposition process and of crystalline carbon by a pyrolytic process. These coatings, together with a graphite coating previously developed, were evaluated in pressure-bonded fuel elements for their effectiveness … more
Date: May 11, 1960
Creator: Paprocki, Stan J.; Hodge, Edwin S.; Layer, Edwin H.; Wintucky, Edwin G.; Gripshover, Paul J. & Carmichael, Donald C.
open access

High Velocity Shock Testing, Equipment and Methods

Description: The need for special high velocity shock testing is pointed out and equipment that has been developed to meet these needs is discussed. The concept of velocity-change and its importance in shock-testing technology is brought out. The three types of equipment discussed are: accelerated drop testers, pneumatic actuators, and air guns. Examples of each type and their capabilities and limitations are presented.
Date: July 11, 1960
Creator: Walker, Walter W.
open access

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.
open access

Irradiation effects on Zircaloy-2-uranium bonds

Description: The failure mechanics of high exposure, in-reactor coextruded fuel rods are quite different from those of defected unirradiated rods. The appearance and corrosion behavior of the high-exposure in-reactor failures suggests that the strength of the coextruded Zircaloy-2 to uranium bond has deteriorated. Notch-fracture tests, in which the strength of the Zircaloy-2 clad to uranium bond is evaluated in a qualitative manner, suggests that the bond strength has not deteriorated to the degree indicate… more
Date: April 11, 1960
Creator: Goffard, J. W.
open access

Laboratory data for review of outlet water temperature limits for BDF type reactors

Description: A knowledge of the thermal and hydraulic conditions within a reactor fuel channel during an inadvertent flow reduction is needed to establish reactor operating limits. Such limits, which are based on outlet water temperature, are called ``trip-after-instability`` limits by the reactor operating personnel. Laboratory experiments were performed to update the knowledge of such conditions in a BDF reactor type fuel channel while using internally and externally cooled fuel elements (I&E`s) at tube p… more
Date: December 11, 1960
Creator: Waters, E. D. & Fitzsimmons, D. E.
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.
open access

LOSS-OF-PRESSURE ACCIDENT--HOT LEG PIPING FAILURE (BLOWER BEHAVIOR CONSIDERED)

Description: A study was made to determine pressure differentials across coolant system components by considering the blowers' influence during the transient state following a rupture in one hot leg of the Experimental Gas Cooled Reactor Coolant System. Results are presented in tables and graphs. It was concluded that a large instantaneous rupture of the reactor coolant system results in lifting the core when the entire graphite area is exposed to the differential. The forces depend on the type of gas … more
Date: January 11, 1960
Creator: Landoni, J. A.
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