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Tracers, Transfer Through Membranes, and Coefficients of Transfer

Description: From abstract: "The rate of flow of a tagged species of a material substance through a permeable membrane is proportional to the rate of flow of the substance itself when, and only when, the species mol [sic] fraction of the substance is the name on both sides of the barrier. The ratio of the osmotic transfer coefficient of a substance in a particular barrier to the exchange coefficient, determinable with a tracer, is greater than one."
Date: 1962
Creator: Nims, Leslie F.
Partner: UNT Libraries Government Documents Department

Determination of Diffusion Cooling in Graphite by Measurement of the Average Neutron Velocity

Description: From Abstract: "The diffusion cooling coefficient in graphite has been determined by measuring the change in the asymptotic average velocity with buckling, by pulsed neutron methods. The times necessary to establish equilibrium spectra in graphite and heavy water have been measured and are reported."
Date: January 2, 1962
Creator: Starr, E. & De Villiers, J. W. L. (Jacobus Wynand Louw)
Partner: UNT Libraries Government Documents Department

Preliminary Study of a Uranium - Bismuth Liquid Fuel Power Reactor L. F. R . 2

Description: Technical report and preliminary design calculations describing a type of liquid fuel reactor adaptable for production or breeding on a U-233 cycle based on data at Brookhaven National Laboratory. Describes design calculations for generating significant amounts of power and neutrons by use of uranium-bismuth solutions with fused salts in the reactor system.
Date: April 27, 1951
Creator: Gurinsky, D. H.; Kaplan, I.; Miles, F. T.; Williams, C. & Winsche, W. E.
Partner: UNT Libraries Government Documents Department

Plate Efficiency in the Exchange of Deuterium Between Ammonia and Hydrogen

Description: Technical report outlining measurements of the equilibrium in the exchange of deuterium between ammonia and hydrogen and of the kinetics of this reaction. Details a series of tests carried out to measure Murphree plate efficiencies.
Date: December 3, 1951
Creator: Perlman, Morris L. & Bigeleisen, Jacob
Partner: UNT Libraries Government Documents Department

Progress Report of the Reactor Science and Engineering Department; January 1 - March 31

Description: Technical report including all work on the liquid metal fuel reactor and normal water enriched uranium reactor component test projects. Includes some studies on the BNL research reactor, shielding, BrF3 extractive distillation, metallurgy, and a portion of the ultimate disposal treatment of purex wastes are included. (From Summary)
Date: 1952
Creator: Williams, Clarke
Partner: UNT Libraries Government Documents Department

Conference on Waste Processing; Meeting of the U.S. Atomic Energy Commission Waste Processing Committee, March 27- 28, 1950; Section 2. Evaporation

Description: Technical report summarizing the waste problems of the Brookhaven National Laboratory site and solutions to problems of nuclear waste evaporation; outline of the second session for the March 27-28, 1950 meeting of the U.S. Atomic Energy Commission Waste Processing Committee at Brookhaven National Laboratory.
Date: 1950
Creator: Hayner, J. H. & Manowitz, B.
Partner: UNT Libraries Government Documents Department

Conference on Waste Processing; Meeting of the U.S. Atomic Energy Commission Waste Processing Committee March 27-28, 1950; Section 1. Brookhaven National Laboratory Waste Problems

Description: Technical report summarizing the waste problems of the Brookhaven National Laboratory site and the integration of projects constituting the need for intensive and extended research into the development of processes, equipment, and systems to dispose of this nuclear waste. This report also outlines the first session for the March 27-28, 1950 meeting of the Committee at Brookhaven National Laboratory.
Date: 1950
Creator: Hayner, J. H. & Manowitz, B.
Partner: UNT Libraries Government Documents Department

A Continuous Fission Product Separation Process; I. Removal of the Rare Earths (Lanthanum Cerium, Praseodymium, and Neodymium) From a Typical Liquid Bismuth-Uranium Reactor Fuel

Description: Technical report investigating the distribution of rare earth elements between a liquid bismuth-uranium solution and fused KCI-LiCi mixtures. Report warrants further research on the liquid bismuth-uranium-fused salt system due to the benefit of continuous fission removal processes.
Date: July 1, 1951
Creator: Bareis, D. W.
Partner: UNT Libraries Government Documents Department

An Experimental and Theoretical Study of the Subcritical BNL Reactor

Description: Technical report outlining the theoretical study of the sub-critical BNL (Brookhaven National Laboratory) reactor, and a comparison of reactor performance with the purpose of presenting the experimental results of the experimental methods. Presents experimental results and and a detailed discussion of the experimental methods along with theoretical analysis and evaluation of the results.
Date: June 15, 1950
Creator: Cwernick, J.; Kaplan, I.; Kunstadter, J.; Sailor, V. & Williams, C.
Partner: UNT Libraries Government Documents Department

Nuclear Reactor Progress Report

Description: Technical report describing the building of safety devices and features for the Oak Ridge reactor by the Reactor Safeguard Committee of the Atomic Energy Commission. Outlines the difficulties encountered in detailed design and construction operations for the facility.
Date: October 1, 1948
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department

Evaluation of Carbagel Process for Air Refrigeration for Use With BNL Reactor

Description: Technical report outlining the use of the Carbagel process in nuclear reactors, its technical feasibility, and case studies of the Carbagel process and its theoretical and technical use for reactors such as the Brookhaven National Laboratory reactor.
Date: April 12, 1950
Creator: Winsche, W. E.
Partner: UNT Libraries Government Documents Department

Liquid Reactor Fuels: Bismuth-Uranium System

Description: Technical report about the liquidus curve for the nuclear reactors bismuth-uranium system and the need for a suitable container for this fuel.
Date: September 15, 1950
Creator: Bareis, D. W.
Partner: UNT Libraries Government Documents Department

On the Structure of Sperm Whale Myoglobin. [Part] 1, The Amino Acid Composition and Terminal Groups of the Chromatographically Purified Protein

Description: The report objective is to establish the amino acid composition of sperm whale myoglobin. From Summary: "The homoprotein that comprises 96% by weight of the protein present in crystalline sperm whale myoglobin may be received into at least five components by chromatography on the carboxylic resin IRC-50."
Date: March 26, 1962
Creator: Edmundson, A. B. & Hirs, C. H. W.
Partner: UNT Libraries Government Documents Department

Classified Progress Report of the Reactor Science and Engineering Department; April 1 - June 30, 1950

Description: Technical report outlining the progress of reactor completion and startup events by the Reactor Theory, Physics, Radioisotope Development, Geology, Meteorology, Waste Concentration, and Waste Disposal groups in the Reactor Science and Engineering Department of Brookhaven National Laboratory.
Date: 1950
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department

The Angular Dependence of Thermal Neutron Spectra in Lattices

Description: This technical report discusses techniques that have been developed for "computing the angular thermal flux spectrum emerging from a lattice. These methods are applied to water lattices and it is found that the computed spectra are sensitive to the geometrical description of the lattice, but insensitive to the anisotropic scattering by water. Comparisons with measured spectra indicate that corrections for gradients and the finite size of the experimental lattice are important." -- from abstract (p. 3).
Date: January 1962
Creator: Honeck, Henry C. & Takahashi, Hiroshi
Partner: UNT Libraries Government Documents Department

Classified Progress Report of the Reactor Science and Engineering Department for the Year 1949

Description: Technical report covering classified activities of the Department of Reactor Science and Engineering since its inception in January, 1949. This if focused on the research, evaluation, and redesign of the reactor as well as the tests on various reactor components and engineering design to correct structural defects as they have become evident through reactor use.
Date: 1949
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department

Classified Progress Report of the Reactor Science and Engineering Department January 1 - March 31, 1950

Description: Technical report indicating the progress made in the first quarter of 1950 only for the classified projects in the Reactor Science and Engineering Department, including continuous processing breeder blanket studies, sub-critical experiments, and metallurgical experiments like fluid fuels, materials testing, reactor reconstruction, and reactor component testing and service.
Date: 1950
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department

The Concentration of Deuterium by Chemical Exchange Between Hydrogen and Ammonia

Description: Technical report describing the results of the chemical reaction between potassium amide and liquid ammonia and the exchange of hydrogen between hydrogen gas and liquid ammonia. This report finds that the reactions may be sufficiently rapid to be useful for isotope separations on a larger scale.
Date: December 15, 1951
Creator: Perlman, M. L & Bigeleisen, J.
Partner: UNT Libraries Government Documents Department