4,891 Matching Results

Search Results

Results: 1 - 24 next
open access

1. K+ Charge Exchange - Search For K+ Charge Exchange

Description: An experiment was designed utilizing a charge-exchange reaction to study the decay and interactions of the neutral K mesons produced. The experiment produced no events that could be interpreted as either the decay or interaction of neutral K mesons. The nature of the experiment and the possible explanations of this unexpected result are presented in this paper.
Date: July 29, 1959
Creator: Birge, Robert W.; Courant, Hans J.; Lanou, Robert E., Jr. & Whitehead, Marian N.
Partner: UNT Libraries Government Documents Department
open access

3 Plant Radiation Study Interim Report #5- Part II Data on Gamma Shielding of Special Plutonium Samples

Description: The calculation of shielding the thickness for plutonium is complicated by the many different energies represented in the gamma radiation emitted during decay of the plutonium isotopes. Dose rate predictions are also frequently confused by gamma from varying content of fission product impurities in the plutonium, as well as other gamma radiation induced through alpha and neutron particle absorption within the source material or its environment. After assumptions are made for these many factors… more
Date: October 22, 1959
Creator: Moulthrop, H. A.
Partner: UNT Libraries Government Documents Department
open access

6.70 EV Resonance in U²³⁸

Description: "Using the Brookhaven fast chopper, transmission curves were obtained for the 6.70 +/- .06 ev resonance in U238 using four different thicknesses of natural uranium metal." The measurements for the transmission curves are summarized in the table provided.
Date: November 9, 1953
Creator: Levin, Jules S.
Partner: UNT Libraries Government Documents Department
open access

9-Zoom : A One-Dimensional, Multigroup, Neutron Diffusion Theory Reactor Code for the IBM 709

Description: The following document describes the usage and purpose of the neutron diffusion theory reactor program 9-Zoom, a memory-contained program that takes advantage of 709 features such as, for example, preferential order of multiply by zero, and for small problems approaches input-output limitations with excellent convergence properties.
Date: August 25, 1959
Creator: Stone, S. P.; Collins, E. T. & Lenihan, S. R.
Partner: UNT Libraries Government Documents Department
open access

A 10-Megacycle Transition Binary Counter

Description: In the field of high-speed counting, circuits having low power requirements are needed. The design of a 10-megacycle transistor binary counter was undertaken and completed.
Date: September 19, 1956
Creator: Holliday, Dennis
Partner: UNT Libraries Government Documents Department
open access

D-10 Timer

Description: The D-10 timer is designed to operate directly on a negative voltage step and, despite its simple circuitry, is capable of producing extremely accurate time delays.
Date: April 16, 1957
Creator: Creveling, R.
Partner: UNT Libraries Government Documents Department
open access

14-Year 113Cd

Description: The half lives of Cd/sup 113m/ and Cd/sup 115m/ have been redetermined to be 14 sintering time 2 years and 44.2 sintering time 0.5 days, respectively. The ratio of Cd/sup 113m/Cd/sup 115m/ yields from thermal-neutron fission of U/sup 235/ is 0.27 sintering time 0.03, and the ratio of (n, ) formation cross sections is 0.31 sintering time 0.03. Combination of these ratios with literature values for the Cd/sup 115m/ fission yield and (n, ) formation cross section gives (1.9 sintering time 0.2) x 1… more
Date: October 31, 1959
Creator: Wahl, Arthur C.
Partner: UNT Libraries Government Documents Department
open access

"25" Critically Consultation with J. W. Morfitt : April 3, 1950

Description: Summary: "Criticality was considered impossible in any contingency encountered in practice under either of the following conditions which include no safety factor: (a) In any isolated cylinder not more than 5 in. in disruptor, if the total amount of U235 present does not exceed 7.5 Eg. (b) In an isolated vessel of any shape and size, if the total amount of U235 present does not exceed 880 g. An "isolated" vessel is one which does not "see" more than 0.1 [...] other vessels containing fissionabl… more
Date: April 3, 1950
Creator: Merrill, E. T. & Sege, G.
Partner: UNT Libraries Government Documents Department
open access

A 37,500 KW Power Reactor with Competitive Possibilities

Description: The following report follows the study on economics of nuclear power generation using a light water reactor.
Date: February 26, 1954
Creator: Thompson, W. I. & Cohen, Karl
Partner: UNT Libraries Government Documents Department
open access

An 80 Megawatt Aqueous Homogeneous Burner Reactor. Reactor Design and Feasibility Problem

Description: An 80 Mw aqueous homogeneous burner reactor suitable for producing 20 Mw of electricity at a remote location is described. The reactor fuel consists of a light water uranyl sulfate solution which acts as its own moderator and coolant. The uranium is highly enriched (93% U/sup 235/). The primary considerations for the design were simplicity and reliability of the components, automatic demand control and safe for any load change, full xenon override not required, possibility of construction withi… more
Date: August 1957
Creator: Chapman, R. H.; Collins, H. L.; Dollard, W. J.; Fieno, D.; Hernandez-Fragoso, J.; Miller, J. W. et al.
Partner: UNT Libraries Government Documents Department
open access

200 MW Nuclear Power Station Using a Natural Uranium, Organic Cooled, Heavy Water Moderated, Heterogeneous Power Reactor : Reactor Design and Feasibility Study

Description: A preliminary design and feasibility study is presented for an organic cooled, heavy water moderated, natural uranium fuel, heterogeneous reactor for a central station power plant with an electrical capability of 200 Mw. This study indicates that such a plant is capable of producing electrical energy in the range of 0 to 7 mills/kwh with burnups of the order of 3000 Mwd/ ton. The use of organic coolants permits high temperature operation at low pressure and thereby eliminates the necessity for … more
Date: August 1957
Creator: Veras, A. F.; Beal, F. S.; Hartfield, G. L.; Irwin, H. D.; Licitra, E. A.; Lill, H. I., Jr. et al.
Partner: UNT Libraries Government Documents Department
open access

327 Basin Aluminum Corrosion Test

Description: An investigation of corrosion in the 327 Building's water storage basin was made to determine whether the static storage of aluminum jacketed fuel elements could cause corrosion effects that would interfere with studies of in-pile corrosion.
Date: February 9, 1956
Creator: Mallett, G. R.
Partner: UNT Libraries Government Documents Department
open access

A 704 Program for Computing Thermal Neutron Spectra in Infinite Homogenous Media

Description: A flexible program has been prepared for solution of the neutron balance equation in an infinite homogeneous medium. This program is specifically designed for studying the effects of varying the energy transfer kernel on the resultant neutron spectrum. A rapidly converging iterative procedure is employed. The equation to be solved and the specific input information required by the program in order to compute spectra are explicitly stated. No discussion of the physics of the problem is given.
Date: November 24, 1958
Creator: Nelkin, M S.
Partner: UNT Libraries Government Documents Department
open access

709 Program for Reduction of Exponential Pile Data

Description: A multi-purpose program for processing exponential data has been prepared for the 709 computer. The main purposes of the program is to compute the material buckling from raw data (given counts, time, and counter information) or from previously calculated Athermal's. It is also possible to compute only CeCh (end and harmonic corrections) for a given B11 or series if B11's no counting data being entered. In every case, pile measurements must be submitted as input for corrections.
Date: August 20, 1959
Creator: Matsumoto, D. D.
Partner: UNT Libraries Government Documents Department
open access

1706 KE Water Treatment for Out-of-Reactor Test Facilities.

Description: Water treatment systems for preparing and maintaining high purity water in out-of-reactor or in-reactor test oops are becoming increasingly important. In out0of-reactor experiments the presence of ionic impurities in the water has a marked influence on film formation and corrosion rates. It is therefore , imperative that these impurities be maintained at the lower practical concentration.
Date: March 30, 1959
Creator: Demmitt, Thomas F.
Partner: UNT Libraries Government Documents Department
open access

1706-KER Coolant Test Facility Operations Manual

Description: This procedure is intended to be used as: 1. An instruction and guide for operation of the KER loops. 2. To aid in familiarization and understanding of the general operation of the loops. 3. To prevent lost time due to errors in loop operation. The procedure is not meant to be completely comprehensive in all details of loop operation.
Date: January 23, 1958
Creator: Dulin, R. V.
Partner: UNT Libraries Government Documents Department
open access

1A Reactor Inlet Hydraulic Valve Position Detector Temperature. Section I. Core I, Seed 1. Test Results DL-S-258-S, RNI-3

Description: The purpose of the test was to determine the internal temperature of the valve position detector for the 1A reactor inlet hydraulic valve with the plant at normal pressure and temperature and at power. The normal operating temperatures for the valve position detector on the 1A reactor inlet hydraulic valve range from a minimum of 287 F to a maximum of 294.7 F.
Date: November 20, 1959
Partner: UNT Libraries Government Documents Department
open access

Abnormal grain growth in nickel-base heat-resistant alloys

Description: From Introduction: "The data included in this report for Nimonic 80A alloy, for instance, represent experiments carried out to help clarify a production problem of grain-size control in an alloy which has been extensively used. The general procedure of the investigation was to carry out controlled laboratory experiments on samples of bar stock to find conditions of heating and hot-working which resulted in abnormal grain growth."
Date: December 1957
Creator: Decker, R. F.; Rush, A. I.; Dano, A. G. & Freeman, J. W.
Partner: UNT Libraries Government Documents Department
open access

An Abrasive Cutoff Machine for Metallurgical Research on Radioactive Materials

Description: An abrasive cutoff machine design, based upon a previous model, (1) was undertaken to provide for the sampling of radioactive material. the design objective was; first, to provide samples for metallographic examination, second, to provide samples for physical and mechanical property testing, and, third, to meet the following design requirements: 1. Remote operation. 2. Airborne contamination control. 3. Radioactive waste collection. 4. Remote maintenance.
Date: January 5, 1957
Creator: Boyd, C. L.
Partner: UNT Libraries Government Documents Department
open access

Absolute Cross Sections of the Reaction P + P - w+ + d

Description: Absolute differential cross sections for the reaction p + p - w+ + d were obtained by detecting meson-deuteron coincidences produced by passing the 340-Mev external proton beam of the Berkeley synchro-cyclotron through a liquid hydrogen target.
Date: April 23, 1953
Creator: Crawford, Frank Stevens, Jr.
Partner: UNT Libraries Government Documents Department
open access

Absolute Measurement of Eta by the Manganese Bath Technique

Description: This is a short description of an experiment, now in progress, to measure eta of U233, and an estimate of the various errors involved in the experiment. It seems that a value for eta can be obtained with a precision of 1% or better.
Date: January 20, 1959
Creator: deSaussure, G. & Macklin, R. L.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen