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Savannah River Project Site Report: 30,000 KW Prototype Partically Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission Idaho Operations Office

Description: Report describing a modified prototype of a nuclear reactor that uses partially uranium-enriched fuel and is cooled by helium. The construction site, site safety aspects, and design and construction costs are included.
Date: March 1959
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
open access

Leaching and Precipitation Tests on Grants Ores

Description: Leaching tests were run on two samples from the Grants area in New Mexico. Uranium extractions of 94 per cent were obtained by leaching Sample 6-1 with solutions containing 240 lbs. of Na2CO3 and 60 lbs. of NaHCO3 per ton and by leaching Sample 6-2 with 270 lbs. of Na2CO3 and 180 lbs. of NaHCO3 per ton. Cyclic tests were completed using caustic precipitation of the leach liquor.
Date: September 10, 1951
Creator: Abrams, Charles S. & George, D'Arcy R.
open access

Preliminary Studies of the Adsorption of Uranium in a Resin-In-Pulp System

Description: Data were obtained in non-flowing and flowing (continuous) batch adsorption systems to serve as a guide to the operating conditions that should be used in a resin-in-pulp adsorption system for the recovery of uranium from ores.
Date: July 27, 1953
Creator: Abrams, Charles S. & Kaufman, David
open access

Preliminary Leaching Tests for the Extraction of Uranium From Various Monticello Stockpile Ores

Description: In a section of the area occupied by the Atomic Energy Commission in Grand Junction, Colorado, a pilot plant is being erected to test a resin-in-pulp process. The process is based on the adsorption of uranium by resin from acid pulps. The first ores to be treated at this plant will be Monticello Stockpile Material. Samples of the various stockpiles sere subjected to a series of leaching, filtering and settling tests, the results of which are presented in this report.
Date: March 2, 1953
Creator: Abrams, Charles S.; Moulton, Harry D. & Viklund, Hans I.
open access

Calculation of k-o in a Uranium-Graphite Lattice

Description: Since the 25 content of the uranium to be used in a MTA multiplying lattice is quite uncertain at present, it is necessary to assume various degrees of depletion in order to estimate the multiplication constant K-o and the production of 49 in an infinite uranium-graphite lattice
Date: February 8, 1951
Creator: Adelman, F.
open access

Three Group Equations for a Multiplying Medium

Description: In the past it was felt that the easiest way to treat a three group equation for a MTA lattice was to solve it without certain terms. This iterative procedure converged rapidly for a medium with depleted uranium fuel, and in fact, a second iteration was not needed.
Date: June 11, 1952
Creator: Adelman, F. L.
open access

Diffusion Equation Green's Functions for Box Problems

Description: The use of diffusion theory to attempt to reproduce the chemical data of Hicks and Stevenson for the spatial distribution of neutrons in a solid block of uranium that is bombarded by 190 Mev neutrons is described.
Date: December 27, 1951
Creator: Adelman, F.; Lepore, J. & Rosenblum, M.
open access

Energy Spectrum of Neutrons from 3-10 MEV

Description: The energy distributions of neutrons in the 3-10 Mev energy range resulting from the bombardment of thin U targets are being investigated by the measurement of proton recoils in photographic plates.
Date: February 11, 1952
Creator: Adelman, Frank
open access

Stability of Florothene Under Exposure to Gamma Radiation

Description: The stability of fluorothene (polytrifluorochloroethylene, Kel-F) to gamma radiation has been investigated to estimate the probable life expectancy of fluorothene equipment exposed to Purex process solutions. Samples of fluorothene were exposed to total gamma radiation dosages up to 10 degree R. The results of these tests substantiate the findings reported by Sisman and Bopp in their compilation of data on the affects of radiation on plastics.
Date: July 6, 1956
Creator: Adler, K. L.
open access

A Study of Efficiencies and Pressure Drop Characteristics of Air-Filtering Media

Description: Removal of particles from air is discussed in terms of three classes of filtering media--air-sampling, respirator, and air-cleaning. Plots of efficiency versus filtering velocity are presented. The pressure drop characteristics of the filters are discussed in terms of initial pressure drops of the clean filters, variations in pressure drop of the individual filters, and comparison of loading rates.
Date: August 10, 1953
Creator: Adley, F. E.; Scott, R. H. & Gill, W. E.
open access

An Evaluation of Mercury Cooled Breeder Reactors

Description: Abstract: The technical feasibility and economic potential of fast breeder power reactor systems cooled with boiling mercury have been investigated by American-Standard under the United States Atomic Energy Commission's New Reactor Concepts Evaluation Program.
Date: October 13, 1959
Creator: Advanced Technology Laboratories
open access

Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959

Description: Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design crit… more
Date: May 25, 1959
Creator: Aerojet-General Corporation
open access

Program Study Report Plutonium Fuel Cycle

Description: From introduction: "The development and demonstration of the natural uranium reprocessed plutonium cycle in power reactors is an important phase of the peaceful applications of nuclear energy."
Date: July 30, 1956
Creator: Albaugh, F. W. & Fryar, R. M.
open access

An anticoincidence gamma ray scintillation spectrometer

Description: From abstract: "A new type of scintillation spectrometer is described. It is designed to suppress signals arising from incident photons that are not completely absorbed in the primary detecting NaI(T1) crystal."
Date: 1952
Creator: Albert, Richard D.
open access

Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design

Description: Preface: The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary … more
Date: February 28, 1959
Creator: Alco Products (Firm)
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