114 Matching Results

Search Results

Results: 1 - 24 next
open access

Microminiaturization Techniques for Communication Equipment

Description: Report discussing a study initiated to investigate and apply techniques of microminiaturization to circuits designed for high reliability performance with two goals: (1) to develop ultra-reliability design techniques in communication equipment, and (2) to microminiaturize the resulting circuits.Compiled in the report are information and instructions to guide transistor circuit engineers in designing semiconductor circuits that lend themselves to microminiaturization. (Abstract)
Date: September 1961
Creator: Anderson, George
Partner: UNT Libraries Government Documents Department
open access

Radioactivation Analysis

Description: The development of nuclear reactors and other sources of nuclear particles has provided the analyst with a new method which has been successfully applied to the determination of microgram and even submicrogram quantities of many elements. In this method, known as "radioactivation analysis," the element to be determined is "activated" through some type of nuclear reaction which produces a radioactive isotope of the element. Since the radioisotope produced decays with its own characteristic radia… more
Date: September 22, 1961
Creator: Leddicotte, G. W.
Partner: UNT Libraries Government Documents Department
open access

Thermodynamic Properties Of Gaseous Metal Dihalides

Description: The second and third law methods of thermodynamics are used to obtain the enthalpies of vaporization of the halides of Be, Mg, Ca, Sr, Ba, Zn, Cd, Hg, Sn, Pb, Ti, V, Cr, Mn, Fe, Co, Ni and Cu. Molecular and free energy data necessary for such calculations are presented. The structure of bonding in these molecules is briefly discussed.
Date: September 1961
Creator: Brewer, Leo, 1919-2005; Somayajulu, G. R. & Brackett, Elizabeth
Partner: UNT Libraries Government Documents Department
open access

PM-3A Nuclear Power Plant Secondary Shield Design

Description: "The design, analysis, and selection of system components for functions related to secondary shielding and associated auxiliary systems for the Antarctic PM-3A Nuclear Power Plant are described. Backfill material characteristics, shielding and activation analyses, heat transfer analysis, backfill cooling system, water exclusion and removal system, and instrumentation and control are discussed."
Date: September 1961
Creator: Siler, W C
Partner: UNT Libraries Government Documents Department
open access

Comparison of Radiation-Induced Graft Copolymerization Untilizing Electron Accelerators and Isotope Sources as Radiation Initiators

Description: "A comparison of grafting to two thicknesses of polypropylene film is made using isotope and electron accelerator initiation. The results indicate that the grafting of methacrylic acid: styrene to polypropylene is mainly a surface reaction."
Date: September 12, 1961
Creator: Odian, George; Oliver, William F. & Pierre, Karl
Partner: UNT Libraries Government Documents Department
open access

Extraction of Beryllium by Triisooctylamine : the Effect of the Anionic Complexing Agent

Description: The extraction of beryllium by triisooctylamine is measured over the pH range from 1 to 10, in the presence of malonic, maleic, succinic, phthalic, and salicylic acids. Values are obtained for the stability constants of the various metal-acid complexes by potentiometric titration. The degree of extraction is dependent on the abundance of the anionic complex present in the aqueous phase and this is in turn dependent on the strength of the corresponding acid and the stability of the complex. (aut… more
Date: September 1, 1961
Creator: De Bruin, H. J.; Kairaitis, D. & Temple, R. B.
Partner: UNT Libraries Government Documents Department
open access

Hazards Evaluation of the SM-1 Penetrated Gasket

Description: Abstract: This technical report describes the as-constructed SM-1 penetrated gasket designed for SM-1 Core and Flow Instrumentation (Task XIV). This report supplements APAE No. 79, The Summary Hazards Report for Task XIV, and evaluates the effects of a postulated failure of this gasket. The effects of failure on the Maximum Credible Accident are determined and conclusions and recommendations for the use of this gasket are made.
Date: September 8, 1961
Creator: Coombe, J. R.; Gebhardt, F. G. & James, B.
Partner: UNT Libraries Government Documents Department
open access

Hazards Report for Insertion of the PM-1-M-2 Element in the SM-1 Core II

Description: Abstract: This technical report describes the Martin Co. PM-1-M-2 test element and analyzes the potential hazard incurred by its inclusion in the SM-1 Core II. A nuclear analysis develops power distributions and reactivity effects. Hydraulic and thermal analyses develop anticipated burnout heat flux ratios. An evaluation of the risk involved with the inclusion of this element is presented. In view of the narrow margin by which the PM-1-M-2 test element meets the minimum burnout ratios as def… more
Date: September 1, 1961
Creator: Coombe, J. R.; Scoles, J. F.; Brondel, J. O. & Lee, D. H.
Partner: UNT Libraries Government Documents Department
open access

Consolidated Edison Thorium Reactor: Core Assembly Physics and Zero Power Tests Report

Description: Results of zero power tests to confirm the nuclear design of the Consolidated Edison Thorium Reactor Core are presented. The maximum core reactivity, control rod worths, and power distribution were measured.
Date: September 1961
Creator: Edlund, Milton C. (Milton Carl), 1924-; Ball, R. M.; Deddens, J. C. & Flickinger, R. F.
Partner: UNT Libraries Government Documents Department
open access

Design Criteria for Irradiated Vessels Task 6.0 Summary Report

Description: Abstract: This technical report presents design criteria to prevent the brittle fracture of ferritic reactor vessels that cold occur as a result of the rise in NDT caused by fast neutron irradiation. The criteria require that maximum principal stress in the vessel does not exceed 18 percent of yield stress at temperatures below NDT + 60 degree F. Under certain conditions the allowable stress may be based on the irradiated yield stress. A discussion of brittle fracture and an explanation of the … more
Date: September 29, 1961
Creator: McLaughlin, D. W.
Partner: UNT Libraries Government Documents Department
open access

Steady State and Transient Thermal and Hydraulic Analysis of SM-2 Termination Report

Description: Abstract: Thermal characteristics of the SM-2 core were analyzed at steady state and loss of flow conditions. For steady state operation, the steady state code STDY-3 was used. For transients during a loss of flow accident, ART-02, a one-dimensional code, was used. This analysis indicates the SM-2 core is safe from burnout under steady state operation at design power level (28 tMW) because (1) no nucleate boiling exists, and (2) the minimum burnout ratio is above 2.0. The core is safe from burn… more
Date: September 8, 1961
Creator: Segalman, I. & Bradley, P. L.
Partner: UNT Libraries Government Documents Department
open access

Fuels Preparation Department monthly report, August 1961

Description: This report is divided into: production (fuel elements), engineering (present reactor fuels, N Reactor development), and general (AlSi shop). (DLC)
Date: September 7, 1961
Creator: Dickeman, R. L.
Partner: UNT Libraries Government Documents Department
open access

Investigations of Ice-Free Sites for Aircraft Landings in East Greenland, 1959

Description: Abstract: "Thirty-three specific landing sites were investigated in the ice-free land area of East Greenland between Scores by Sund and Loch Fyne. Eight of these are considered suitable for emergency landings in summer by heavy cargo planes, and several more for light cargo planes. Several sites were investigated for the Royal Greenland Trade Department in the Scorebysund - Kap Tobin area. A 1550-foot airstrip was located on a gravel terrace in the Jaettedal, eight miles northwest of Kap Tobin,… more
Date: September 1961
Creator: Hartshorn, Joseph Harold; Stoertz, George E.; Kover, Allan N. & Davis, Stanley N.
Partner: UNT Libraries Government Documents Department
open access

TOE work sheets

Description: This report provides operational worksheets detailing charge/discharge, maintenance, fuel element ruptures, leaks, tube replacements, and production data.
Date: September 14, 1961
Creator: Chatten, J. C. L.
Partner: UNT Libraries Government Documents Department
open access

Reactivity and graphite temperature effects of a helium-nitrogen atmosphere. Final report of PT IP-358-AC

Description: The purpose of the production test was to {open_quotes}investigate the reactivity and temperature effects and the associated operating problems resulting from the use of nitrogen instead of carbon dioxide as a constituent of the K Reactor atmosphere.{close_quotes} This report summarizes the reactivity and reactivity-associated graphite temperature effects observed during the first four months of the test which was initiated at KE Reactor on December 5, 1960.
Date: September 29, 1961
Creator: Bailey, G. F.
Partner: UNT Libraries Government Documents Department
open access

Numerical results of production test IP-326-I, low flow calibration tests at DR and C reactors, and of production test IP-395-I, removal of high tank discharge line strainer gates at B, D, and F reactors

Description: Low flow calibration tests have now been completed at all old reactors as a part of the program to determine the adequacy of the old reactor last ditch water backup system more accurately. In addition, the high tank discharge line strainer gates have been removed at B, D, and F reactors in order to increase the emergency high tank flow rates to the reactors and thereby increase high tank water backup adequacy. The purpose of this document is to list the results of the last two low flow calibrat… more
Date: September 29, 1961
Creator: Benson, J. L.
Partner: UNT Libraries Government Documents Department
open access

NPR Reactor shield calculations

Description: At the request of IPD Personnel, calculations on neutron and gamma attenuation were made for the NPR shield. The calculations were made using a new shielding computer code developed for the IBM 7090. The calculations show the thermal neutron flux, total neutron dose rate, and gamma dose rate distribution through the entire shield assembly. The calculations show that the side and top primary shield design is adequate to reduce the radiation level below design tolerances. The radiation leakage th… more
Date: September 27, 1961
Creator: Peterson, E. G.
Partner: UNT Libraries Government Documents Department
open access

Irradiation effects in hot-pressed fuel elements

Description: Two Hanford hot-pressed fuel elements were irradiated in the Materials Test Reactor to an approximate exposure of 1000 MWD/T (0. 11 a/o burnup or 5. 8 {times} 10{sup 19} fissions/CM{sup 3}). One element represented the best bond quality, the other element represented a poor bond due to unoutgassed uranium. After irradiation, radiometallurgical examination revealed extensive bond separation in the unoutgassed fuel element. The Ni{sub 2}Al{sub 3} layer thickened slightly and cracks were observed … more
Date: September 1, 1961
Creator: Tverberg, J. C.
Partner: UNT Libraries Government Documents Department
open access

Fabrication Costs

Description: This document from the principal engineer of the manufacturing section at Hanford calls attention to irreconcilable costs for two fuel fabrication studies. Specifically, the major trouble areas appear to be in refinery, green salt and machining steps.
Date: September 13, 1961
Creator: Lang, L. W.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen