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Apparent viscosity of simulated underground metal waste slurries
From introduction: "This report presents the apparent viscosities of supernate-sludge slurries prepared synthetically to simulate the conditions known to exist in the waste storage tanks, but with fission products and plutonium absent."
Date:
June 20, 1950
Creator:
Allen, A. W.
System:
The UNT Digital Library
The Effect of the Speed of Emission on the Rise of a Plume of Stack Gases
From introduction: "In this report an attempt was made to summarize the results of recent research on the effective height of smoke stacks. In this summary attention is paid only to the case in which the density of the stack effluent is the same as that of the surrounding air."
Date:
November 20, 1950
Creator:
Barad, M. L.
System:
The UNT Digital Library
Techniques for Estimating the Specific Retention Properties of Hanford Soils
Disposal on a specific retention basic of certain radioactive liquid waste solutions emanating from separations from separations plants has been practiced at Hanford since 1944. As used at Hanford, the term "specific retention" is defined as that volume of waste liquids that may be disposed to the soil* and be held against the force of gravity by the molecular attraction between sand grains and the surface tension of the water, when expressed as percent of packed soil volume. In practice it represents the volume of liquid that may be discharged to a disposal pit of known dimensions without leakage to the ground, water, expressed as percent of the total volume of a column of soil with the same cross section as the pit, and extending from the bottom of the pit to the water table. It is recognized that some degree of lateral spreading will occur which has the effect of enlarging the volume of soil contacted by the liquid.
Date:
August 20, 1959
Creator:
Bierschenk, William H.
System:
The UNT Digital Library
Purex Pulse-Column Studies With Unirradiated Uranium: (Development of Specifications for the O.R.N.L. Pilot Plant)
Report summarizing data from Purex tests for pulse column specifications. These test results were used to estimate pilot plant specifications.
Date:
February 20, 1951
Creator:
Bradley, J. G.
System:
The UNT Digital Library
The Analysis of TBP Process Streams for Calcium with the Flame Photometer
Summary: A method was found for determining calcium concentrations in TBP process streams in spite of serious interferences bysodium, ferrous, uranyl, sulfate, phosphate, and sulfamate ions as well as by TBP. The precision attainable varied from sample to sample, depending upon its composition. In general, errors of 20% or greater occurred. The smallest determinable amount of calcium was about 10 mg/1.
Date:
February 20, 1953
Creator:
Brite, D. W.
System:
The UNT Digital Library
Ferrous Sulfamate Stability in the RA System
Objective: "The observations summarized in the present report were made to determine the stability of ferrous and sulfamate ions and sulfamic acid in RA Column scrub solution (RAS) and in aqueous solution comparable to the RA Column feed tee composition (RAFS). Knowledge of the stability of the reducing agent (ferrous iron) is necessary to properly plan the method of preparation and introduction of this component into the RA system and to assure dependable and reproducible performance."
Date:
April 20, 1950
Creator:
Clagett, Fred
System:
The UNT Digital Library
Study Report: High Speed Data Acquisition System for PRTR
High speed data handling and computing systems are coming into increasing use in the automatic control of complex industrial processes. One of the next significant developments in reactor design is believed to be the application of high speed data handling and control systems to nuclear reactors. This document is a study of such a system intended for use with the Plutonium Recycle Test Reactor.
Date:
January 20, 1960
Creator:
Clark, R. G.
System:
The UNT Digital Library
Densitometric Determination of Iron in Plutonium
"The attached report summarizes the work performed in the establishment of an improved spectrographic method for determining iron in plutonium."
Date:
December 20, 1951
Creator:
Daniel, J. L.
System:
The UNT Digital Library
Properties and Settling Rates of 101-U Sludge-Supernate Slurries
This report discusses the settling rates and properties of 101-U sludge when slurried with increasing amounts of synthetic supernatant.
Date:
June 20, 1950
Creator:
Frame, J. M.
System:
The UNT Digital Library
Parameters of Dissolver Equipment Design - Power Fuel Reprocessing
The Interim Power Fuels Reprocessing Program, as established by the Atomic Energy Commission, provides the service of recovering uranium, thorium, plutonium, etc., from irradiated fuels discharged from non-production reactors of both public and private ownership. To provide this service on an interim basis and at minimum capital investment, the Commission has assigned the processing responsibility for the various fuel types to several AEC sites. The sites are to be assigned fuel types most similar to their normal production. As a result, HAPO has been assigned the responsibility for processing the low enrichment uranium and uranium oxide type fuels with isotopic content up to 5% uranium-235. In addition, some plutonium base fuels will be processed at Hanford.
Date:
May 20, 1959
Creator:
Graf, W. A.
System:
The UNT Digital Library
Effect of Gamma Radiation on the Physical Properties of Elastics
This article presents data on the effects of gamma radiation on the physical properties of a number of different classes of plastics materials of construction which were screened to determine their capabilities and limitations for service in applications where ionizing radiation exists. The irradiations were carried out in air at ambient temperature at normal atmospheric pressure to various gamma radiation doses up to 1*10^9 r depending upon the stability of the materials to radiation exposure. The different classes of materials and materials within a class are compared.
Date:
January 20, 1961
Creator:
Harrington, Robert
System:
The UNT Digital Library
Monitoring Survey : Richland to Arco, Period May 9-11, 1952
This report follows an investigation of a cargo truck found contaminated by various radioactive material on a routine trip from Arco, Idaho to the Hanford plant on May 8, 1952. The report analyzes the truck's route in an attempt to find the location of the contaminating region.
Date:
June 20, 1952
Creator:
Honstead, J. F.
System:
The UNT Digital Library
Transistor Pre-Amplifier for Neutron Monitors
In the past several years the use of neutron monitors for Pu concentration monitoring has been expanded in the Chemical Processing Department. Most of these monitors have been quite successful, and considerable effort is being made to improve the operation of both existing and future monitoring systems. One of the major improvements has been the development and use of a transistorized pre-amplifier or impedance matching circuits. This unit solves several problems associated with the use of boron trifluoride (BF3) neutron detectors in process monitoring; e.g., vacuum tube pre-amp failure because heat is not being conducted away.
Date:
April 20, 1960
Creator:
Kelly, P. R.
System:
The UNT Digital Library
Guide to Application of the X-ray Photometer in Chemical Analysis
From summary: "The relative absorptions of X-rays by various substances are listed as a guide to the application of the X-ray photometric method in chemical analysis and to the estimation of interference by extraneous substances."
Date:
June 20, 1952
Creator:
Lambert, Maurice C.
System:
The UNT Digital Library
Corrosion of 2R-2 and 304 Stainless Steel Following the Turco-4501 Decontamination Process.
The build up of contaminated film on the internal surfaces of high temperature in-reactor recirculating water loops has created serious radiation exposure problems to operational and maintenance personnel. A considerable amount of work has been applied to develop an effective decontamination process for the decontamination of these loops and their components.
Date:
April 20, 1959
Creator:
Larrick, A. P. & Lotsinger, R. J.
System:
The UNT Digital Library
Analytical procedures for the metal fabrication process
From introduction: The present report describes further refinements of the apparatus and the method to meet a need for a sensitive determination of carbon in plutonium.
Date:
February 20, 1951
Creator:
Leboeuf, M. B.
System:
The UNT Digital Library
Preliminary Results of the Ratio of PU²³⁹ Fission Cross Section to U²³⁵ Fission Cross Section
This report presents the final results from the investigation of the ratio of Pu-239 fission cross section to U-235 fission cross section. Three sets of plutonium and uranium foils were prepared at KAPL and were investigated to acquire the final results.
Date:
February 20, 1953
Creator:
Leonard, B. R.
System:
The UNT Digital Library
709 Program for Reduction of Exponential Pile Data
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.
System:
The UNT Digital Library
L/R Indicator
The evaluation of the inductance of an electrical component is often important in understanding and operating an electrical circuit. Inductance is defined by several equations, the most common being e= -L d1/dt . This equation defines inductance as the constant which relates the back emf produced in an element to the time-rate-of-change of current.
Date:
May 20, 1960
Creator:
Minor, G. C.
System:
The UNT Digital Library
The Determination of Uranyl Nitrate in Pretreated Hexone by Infrared Absorption Measurements
The following report examines methods to determine uranium nitrate hexahydrate on pretreated hexone in the range of 0 to 40 g./l. by infrared absorption measurements.
Date:
April 20, 1950
Creator:
Moore, R. H.
System:
The UNT Digital Library
An Infrared Absorption Method for TBP After Extraction from an Aqueous Phase
This report describes an improved infrared absorption method to analyze aqueous samples and TBP after extraction. The method described in the following pages is the carbon tetrachloride extraction method.
Date:
September 20, 1951
Creator:
Moore, R. H. & Brite, D. W.
System:
The UNT Digital Library
Distribution of the Actinide Elements in the Molten System: KCI-AICI3-AI
Report of data for the distributions of elements 90 through 96 between molten salt solutions of their chlorides and molten aluminum (or alloy) at 725 Celsius.
Date:
October 20, 1959
Creator:
Moore, R. H. & Lyon, W. L.
System:
The UNT Digital Library
Kinetics of Plutonium Reduction in the Redox IB Column
The following report describes work carried out to investigate whether the Hanford IB column as designed in a previous report will decontaminate the uranium adequately from plutonium, particularly if there's any slowness in either the rate of reduction or transfer of the plutonium.
Date:
March 20, 1951
Creator:
Moore, Robert Lee
System:
The UNT Digital Library
NPR Single Pass Decontamination
The design of NPR shows large quantities of carbon steel pipe and fittings in the front and rear face areas. These are also the area where the most work must be done during an outage, and consequently lower radiation levels are needed here than elsewhere in the piping system. A single pass decontamination of the front and rear piping without going through the entire loop is desirable. Because of the quantities of chemicals and available down time, an effective shorty interval process is needed. This report gives some recent laboratory data on this subject.
Date:
January 20, 1960
Creator:
Neibaur, G. E.
System:
The UNT Digital Library