Search Results

open access

Precise Measurement of Heat of Combustion with a Bomb Calorimeter

Description: From Introduction: "This Monograph describes methods and apparatus used at the National Bureau of Standards in connection with several series of investigations of heats of combustion of aircraft fuels [4, 5, 6, 7]."
Date: February 26, 1960
Creator: Jessup, R. S.
Partner: UNT Libraries Government Documents Department
open access

Transistor Scintillation Spectrometer

Description: Report describing "an AC-operated portable scintillation spectrometer consisting of a preamplifier, a linear pulse amplifier, a single-channel pulse-height analyzer, a linear count-rate meter, a scaler, and a high-voltage power supply. The operation and performance of the circuits are discussed" (p. 3).
Date: February 1960
Creator: Strauss, Michael G.
Partner: UNT Libraries Government Documents Department
open access

Preliminary Design and Hazards Report-Boiling Reactor Experiment V (BORAX V)

Description: From introduction: "The report is preliminary. At the time of writing, the status of the BORAX V project is that design of the reactor buildings and plant, done in collaboration with the architect-engineer with the architect-engineer has been completed and construction has just started; however, the mechanical design of the fuel and cores is still tentative."
Date: February 1960
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department
open access

Description of Facilities and Mechanical Components: Medical Research Reactor (MRR)

Description: Report issued by the Brookhaven National Laboratory discussing the Medical Research Reactor at the Medical Research Center. Design, tests, and operations of the reactor are presented. This report includes tables, illustrations, and photographs.
Date: February 1960
Creator: Godel, Jules B.
Partner: UNT Libraries Government Documents Department
open access

ETR Nuclear Instrumentation : Final Report

Description: Report regarding the primary nuclear instrumentation at the Engineering Test Reactor (ETR) and early difficulties.
Date: February 3, 1960
Creator: Hanson, D. C.
Partner: UNT Libraries Government Documents Department
open access

Homogeneous Reactor Project Progress Report: May-October 1959

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 10, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
Partner: UNT Libraries Government Documents Department
open access

Critical Mass Studies of Plutonium Solutions

Description: Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date: February 15, 1960
Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
Partner: UNT Libraries Government Documents Department
open access

The Liquid Metal Thorium Breeder Reactor

Description: From introduction: "Investigation of breeding potential and technical and economic feasibility of breeding in the Liquid Metal Fuel Reactor concept."
Date: February 1960
Partner: UNT Libraries Government Documents Department
open access

Single tube meltdown incident

Description: In connection with design of rear face fittings for the plant-expansion study currently being conducted we have been asked to determine if rear face pressurization is required for safety reasons and if so, how much. Pressurization of the rear face piping would be used to provide sufficient reverse flow to prevent process tube burnout in the event of complete loss of coolant supply to a single tube by virtus of a front connector failure. Consideration of the effectiveness of rear face pressurization, however, requires a more general look at the problem of single tube meltdown than that provided by considering front fitting failure alone.
Date: February 1, 1960
Creator: Trumble, R. E.
Partner: UNT Libraries Government Documents Department
open access

Radiations from nuclear weapons - signal detectors - NASA program information

Description: This letter is for the purpose of supplying the information that you requested at the meeting of the sub-committee on Project Vela. It is divided into three parts: (1) Radiations from nuclear weapons; (2) Backgrounds for Vela Signal Detectors; (3) Discussion of the NASA program.
Date: February 10, 1960
Creator: White, R. S.
Partner: UNT Libraries Government Documents Department
open access

Heavy Water Moderated Power Reactor Plants [Part 1]: Design Study

Description: From preface: This report is one of a series covering a design study of heavy water moderated power reactor plants with the objective of selection and recommendation of a conceptual design for providing optimum economics with slight fuel enrichment.
Date: February 1960
Partner: UNT Libraries Government Documents Department
open access

A Compendium of Information for Use in Controlling Radiation Emergencies: Including Lecture Notes from a Training Session at Idaho Falls, Idaho, February 12-14, 1958

Description: From introduction: This report is a summary of the lecture material in the training course held at Idaho Falls, Idaho, to familiarize members of radiological assistance teams with information helpful in the response to an unusual accident including release of radioactive materials to a populated environment.
Date: February 1960
Creator: Brodsky, Allen & Beard, G. Victor
Partner: UNT Libraries Government Documents Department
open access

Boiling Water Reactor Study [Part 2, Supplement]: Separate Studies

Description: From summary and conclusions: This study has been made to determine the feasibility of installing reheat steam facilities in conjunction with the selected 306-mw boiling water nuclear power plant.
Date: February 1960
Creator: Ebasco Services Incorporated
Partner: UNT Libraries Government Documents Department
open access

Ignitron Resistance During High-Current Operation

Description: Abstract: "A definition of average conduction resistance for an ignitron is established, and a test bank for determining the value of this resistance is described. Data are reported on four typical ignitron types for several currents in the kiloampere range. Oscillograms are presented to illustrate the change of current with time for a conducting ignitron in a ringing circuit."
Date: February 26, 1960
Creator: Todd, James L.
Partner: UNT Libraries Government Documents Department
open access

An Industrial Gamma Irradiator for Medical Supplies

Description: From foreword: This report presents the preliminary design of an industrial gamma irradiator for the sterilization of medical supplies.
Date: February 19, 1960
Creator: Frankfort, J. Harry; Haram, S. & Wallach, S.
Partner: UNT Libraries Government Documents Department
open access

Synthesis and Fabrication of Refractory Uranium Compounds. Monthly Progress Report No. 6 for January 1 Through January 31, 1960

Description: Preparation of about 1200 g of uranium nitride powder is reported. Experiments indicated that synthesis of mononitride by decomposition of higher nitrides required pro longed heating at high temperature. Chemical analysis of uranium nitride for nitrogen was found to be difficult. Data from analysis of these compounds are tabulated for comparison with calculated composition. Sintering studies of uranium mononitride continued during the report period. Work on uranium silicide formation from the elements without quenching was continued, and effects of crucible material on the synthesis of the material were investigated. (For preceding period see ORC-254.) (J.R.D.)
Date: February 8, 1960
Creator: Taylor, K. M.; Lenie, C. A.; Doherty, P. E.; Hailey, L. N. & Keaty, T. J.
Partner: UNT Libraries Government Documents Department
open access

The Effect of Casting Variables and Heat Treatment on the Tensile Properties of Lead-0.02 to 0.10 Weight Per Cent Calcium Alloy

Description: Some of the controllable variables have been investigated in casting of lead alloys having 0.06 to 0.09 wt.% Ca. The alloy has been found to respond to solution heat-treatment, room-temperature precipitation hardening, and accelerated hardening at 100 ts C. Tensile strengths to 7000 psi have been obtained. (auth)
Date: February 25, 1960
Creator: Townsend, A. B.
Partner: UNT Libraries Government Documents Department
open access

PURIFICATION OF PROMETHIUM BY LIQUID-LIQUID EXTRACTION

Description: A process was developed for separating promethium from raixed fisBion product rare earths by continuous multistage conntercurrent extraction with 100% tri-nbutylphosphste from nitric acid of 12 N or higher concentration. Distribution coefficients at 12 N acidity for aecdamium. promethium. and samarium are 0.43. 0.82, and 1.55, respectively. Single-stage separation factors of 1.9 between successive elements can be maintained throughout the system to give separations dependent only on the number of stages. Extracted values can be recovered from the organic solution by stripping with a smaller volume of dilute nitric acid. A flowsheet for purification of promethium includes one cycle for separation of promethium from neodymum and lighter elements and a secondycle for removal of samarium and heavier elements. Each cycle consists of a series of countercurrent partitioning stages. followed by stripping stages and an evaporator. With 20 stages in the first cycle and 34 stages in the second, a 90% yield of promethium with a purity of 83% can be obtained from a typical mixture of fission product rare earths, assuming essentially perfect mechanical efficiency. An increase to 34 stages in the first cycle would permit a 93% yield of 99% promethium. (auth)
Date: February 12, 1960
Creator: Weaver, B. & Kappelmann, F.A.
Partner: UNT Libraries Government Documents Department
open access

Radial Temperature Profile of Sodium Pool Boiling Heater Assembly

Description: The radial temperature around a sodium reactor heater assembly submerged in water is calculated using a model of the heater cross section found by conformal mapping. Thermocouple readings were also analyzed. When the heat flux is 5 x 10/sup 5/ Btu/hr-ft/sup 2/, a radial temperature drop of about 680 deg C across the center of the thermocouple well is calculated and found to be within 6% of the experimental value. Since most of this drop is across the 0.001-in. helium gap between the heater and its sleeve, it is concluded that the thermocouple will have to be bonded to the sleeve for dependable reading of true sleeve temperature. Drawings of the heater assembly and thermocouple are given. (D. L. C.)
Date: February 22, 1960
Creator: Cappel, H. H.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen