170 Matching Results

Search Results

Results: 1 - 24 next
open access

An Experimental Gamma Irradiator for Hospital Sterilization

Description: From foreword: This report presents the preliminary design of a gamma irradiator intended for use as an experimental hospital sterilizer.
Date: March 7, 1960
Creator: Frankfort, J. Harry; Haram, S. & Wallach, S.
Partner: UNT Libraries Government Documents Department
open access

An Improved Nuclear Measuring Principle : Quarterly Progress Report No. 3 Covering the Period from December 1, 1959 to March 1, 1960

Description: This report is the third in a series of quarterly reports discussing the concept and progression of an improved method in nuclear measuring than the usage of the scintillation counter. This report indicates that in a chopped double beam system, commutation of the detector current permits selection of optimum response time and size of radioactive sources.
Date: March 28, 1960
Creator: Burgwald, G. M. & Stone, C. A.
Partner: UNT Libraries Government Documents Department
open access

Manual of Radiation Protection Standards

Description: "The following is an alphabetical listing of terms and units in common usage at Hanford Atomic Products Operation. Other terms and definitions may be added as the need becomes apparent or as revisions or additional terms are issued by the NCRP and ICRP."
Date: March 1, 1960
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
open access

Alpha correlation

Description: This study was developed to provide a correlation for the evaluation of the pile C{sub RI}/Tube C{sub RI} ratio (alpha value) for each of the Hanford reactors.
Date: March 24, 1960
Creator: Cremer, B. R.
Partner: UNT Libraries Government Documents Department
open access

Status report - C Reactor process tubes

Description: Data have recently been obtained on a number of C-Reactor process tubes. These data make is possible to reassess the current conditions of the tubes in the C-Reactor and hence to re-evaluate the probable data when retubing of the reactor will have to be started. The results of this reassessment are presented below.
Date: March 21, 1960
Creator: Miller, N. R.
Partner: UNT Libraries Government Documents Department
open access

Flux distribution problems at C Reactor

Description: This report discusses an outbreak of ruptures in January and February, 1960, which motivated serious consideration of ail phases of reactor operation so that a combined efforts to reduce rupture potential might be made. Items investigated include mixer location, gas composition control, rod movement, rod configuration, tube power, and the axial flux profile of the reactor.
Date: March 16, 1960
Creator: Chitwood, R. A.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Irradiated OMRE Fuel Elements First Core Loading

Description: Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date: March 1, 1960
Creator: Walter, J. H.; Leirich, J. F. & Calkins, G. D.
Partner: UNT Libraries Government Documents Department
open access

An Advanced Sodium-Graphite Reactor Nuclear Power Plant

Description: Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Partner: UNT Libraries Government Documents Department
open access

An assessment of the zirconium tube program -- C Reactor pilot demonstration installation

Description: Production Test IP-272-A-FP authorizes the installation of up to 100 smooth bore Zircaloy-2 process tubes in C Reactor to demonstrate the feasibility of self-supported fuel elements for production use. An additional 200 zirconium tubes are expected to be delivered by mid-year and con be used to expand the initial demonstration facility. It is the purpose of this document to assess the status of the pilot demonstration program from the B-C Reactor Operation viewpoint.
Date: March 18, 1960
Creator: Amy, G. O.
Partner: UNT Libraries Government Documents Department
open access

Thermal Cycling Tests of Porous Uranium

Description: Abstract: It has been proposed that a fuel element containing porous uranium be used for moderately high temperature applications. In an effort to determine the structural integrity of this type of fuel body, thermal cycling tests have been conducted on porous uranium.
Date: March 15, 1960
Creator: Wilkinson, L. E.
Partner: UNT Libraries Government Documents Department
open access

Vacuum Arc Melting : a Bibliography

Description: This partially annotated bibliography contains 334 references from papers published from 1945 to 1959 and includes references on the consumable - and nonconsumable - electrode vacuum arc melting process. References are also given on electrode preparation, furnace construction and operation, melting, sintering, vacuum techniques, and theory.
Date: March 16, 1960
Creator: Cernak, Elizabeth A.; Doyle, J. & Aconsky, S.
Partner: UNT Libraries Government Documents Department
open access

Design of LCCBM and LCCBN Loops

Description: The special fabrication requirements of the newer columbium alloys, particularly with respect to brazing, stress relieving, weld filler wire, etc., necessitates individual detail and layout drawings for the construction of forced convection corrosion loops from different columbium alloys. Accordingly, it is requested that detail and layout drawings be provided for two forced convection corrosion loops to the specifications outlined.
Date: March 1, 1960
Creator: Coyle, C.E.
Partner: UNT Libraries Government Documents Department
open access

PM-1 Nuclear Power Plant Program: 3rd Quarterly Progress Report, September 1, 1959-November 30, 1959

Description: From abstract: The principal efforts are the furthering of the final design and preparation of specifications for some long-lead components. The entire power plant has been divided, for final design purposes, into 37 subsystems. The status of work on each subsystem at the close of the period is reported.
Date: March 1960
Creator: Martin Company. Nuclear Division.
Partner: UNT Libraries Government Documents Department
open access

Automatic Recording Unit

Description: From abstract: The PT-750 is designed to be used in conjunction with a production tester which requires automatic recording of test data. This manual provides a source of procedures and reference material necessary in automatic recording and in use of the PT-750.
Date: March 29, 1960
Creator: Ross, Frank A.
Partner: UNT Libraries Government Documents Department
open access

Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: January-March 1960

Description: Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant.
Date: March 31, 1960
Partner: UNT Libraries Government Documents Department
open access

Strontium 90 Power Project: Final Summary Report

Description: From summary: The primary purpose of this project is to determine the feasibility of converting reactor waste Strontium-90 into a safe and useful source of electrical energy. Secondary purpose is physical and environmental testing of the power conversion device or thermoelectric couples. This required actual fabrication of a 100-thermal-watt strontium titanate fuel element
Date: March 1960
Partner: UNT Libraries Government Documents Department
open access

Some considerations concerning the accuracy of power level calculations in the context of the control of SS materials

Description: This report investigates a study of the accuracy of the power level calculations. Some characteristics of this calculation can be adduced but the accuracy in the sense of freedom from bias leads to an impasse. It presumes that there is another measurement for comparison purposes for which there are engineering reasons to believe, the inherent error is smaller. For the power level values as calculated by the Foxboro Power Level Calculator no such measurement or calculation exits. However, the ca… more
Date: March 14, 1960
Creator: Stewart, K. B.
Partner: UNT Libraries Government Documents Department
open access

Thermal conductivity studies on various calcined ``cold`` waste: Interim report

Description: Accelerated accumulation of high level radioactive wastes has given impetus to the development of safer and more economical waste storage methods. Several processes for converting these wastes to granular or porous-solid form are being investigated. In any waste volume-reduction process containment of the final material in a sealed metal shell is desirable as a precaution against accidental release of radioactive material. While the final waste forms are generally stable, they are, if uncontain… more
Date: March 11, 1960
Creator: DeMier, W. V.
Partner: UNT Libraries Government Documents Department
open access

Travel to Oak Ridge and Savannah River Plant to Study Processing Plant Containment Philosophy. Trip Report, January 26--29, 1960

Description: This report discusses travel to the Oak Ridge National Laboratory on January 26 and 27 and the Savannah River Laboratory and Plant on January 28 and 29, 1960. The primary objectives of the trip were to obtain information on the containment philosophy for processing plants recently adopted by Oak Ridge National Laboratory and on the Palm Program at Savannah River.
Date: March 9, 1960
Creator: Beard, S. J. & Oberg, G. C.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen