UNT Libraries Government Documents Department - 42 Matching Results

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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
open access

PT-IP-364A: Fabrication of elements brazed closure, 1.6% enriched, 2 w/o zirconium core, KER size tube-tube elements (KAEA1)

Description: The test detailed in this report was designed to obtain irradiation data on the brazed closure on a tube-tube geometry. A 1.6% enriched, 2 w/o zirconium core was chosen for this test to gain a faster exposure rate. The brazing alloy for this test was composed of 84 Zry-2 + 4 Be + 12 Fe.
Date: November 11, 1960
Creator: Tverberg, J. C.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
open access

RADIATION SURVEY OF SIX OF THE THERMAL BARRIERS. CORE 1, SEED 1. Test Results T-643713

Description: A test was performed to determine the radiation levels of the thermal barriers contained in the rod-drive-mechanism housings. Of the six thermal barriers examined, the two-slot type instrumented barriers exhibited higher radiation levels (350 to 2450 mr/hr) than did either the plain type instrumented barrier (1350 mr/hr) or the three noninstrumented barriers (275 to 725 mr/hr). (W.L.H.)
Date: October 11, 1960
Item Type: Refine your search to only Report
open access

Recommended high-tank temperature for maintenance of high-tank backup support

Description: High tank line cleaning and low flow tests at B, D, F, and H Reactors have been completed and results analyzed and related to high tank backup support. Interim provisions have been completed at the old reactors for bleeding and temperature measurement of high tank cooling water. This letter supplies a recommended guide for maintaining high tank temperature control.
Date: October 11, 1960
Creator: Greager, O. H.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
open access

SM-2 Fuel Element Welding Development : Task 5.0

Description: Abstract: Development of welding processes for stainless steel fuel elements, previously initiated by Alco Products, was continued in Task 5. Three objectives were accomplished; (1) development of a suitable reference welding process, (2) evaluation by out-of-pile tests of the structural integrity of reference welded fuel elements, and (3) preparation of specifications and fabrication procedures for the reference welding process.
Date: August 11, 1960
Creator: Harris, R. L.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
open access

TIME-DEPENDENT THERMAL-NEUTRON ENERGY SPECTRA IN A MONOATOMIC HEAVY GAS

Description: The time-dependent thermal neutron energy spectra, for times greater thsn the slowing-down time, were generated in a monoatomic heavy gas using multigroup formalism. These spectra were obtained for infinite as well as finite media of Be and graphite. The behavior of asymptotic energy spectra during the last stage of neutron thermalization and diffusion periods was studied. The thermalization time constant for the establishment of the final Maxwellian velocity distribution of neutrons, in a mono… more
Date: July 11, 1960
Creator: Purohit, S N
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
open access

Supplement A production test IP-314-A, measurement of fuel element temperature changes as the result of film deposition

Description: The objective of this supplement is to determine the effects of operation with neutral pH water on crud deposition on fuel surfaces. This supplement authorizes testing designed to show the effects of coolant pH on the thickness of the crud layer deposited on fuel elements. The supplement will not require additional reactor down time nor will it introduce any hazards to the reactor.
Date: May 11, 1960
Creator: Miller, N. R. & Kratzer, W. K.
Item Type: Refine your search to only Report
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