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CPP Health Physics Manual

Description: Provides detailed instructions for personnel exposed to a variety of occupational hazards including radiation exposure including how to reduce exposure and how to treat if exposed
Date: April 1952
Creator: American Cyanamid Company. Atomic Energy Division.
Partner: UNT Libraries Government Documents Department
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Radiation Damage Problems in the ICPP Barium-140 Separation Process

Description: In the ICPP barium-140 separation process, an MTR fuel element is processed after only two days of cooling. Since the total activity present is of the order of 10(5) curies, it was necessary to investigate the extent and nature of radiation damage to process components, and to devise methods of protecting process solutions where necessary
Date: unknown
Creator: Andelin, Robert L.
Partner: UNT Libraries Government Documents Department
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Waste Management at the Idaho Chemical Processing Plant

Description: The Idaho Chemical Processing Plant recovers the unused uranium from spent, highly enriched reactor fuel elements. Waste management is designed to maintain the release of radioactive and chemical wastes to plant environs within the limits established by AEC Health and Safety.
Date: unknown
Creator: Ayers, A. L. & Burn, P.
Partner: UNT Libraries Government Documents Department
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Maintenance Manual

Description: A prevention maintenance manual establishing the means of reducing maintenance costs through a knowledge of necessity of repair.
Date: unknown
Creator: Beyer, Dean W.
Partner: UNT Libraries Government Documents Department
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Final Progress Report on Organic Coolant Technology-Film Formation Studies

Description: Experiments with various fractions from tritium labelled OMRE used coolant show that the oxygen-rich fractions contribute heavily to film formation in the Pyrolytic Capsule Fouling Test (PCFT). These fractions were not necessarily particulate matter or iron laden.
Date: unknown
Creator: Black, J. F.; Geissler, P. R. & Mackinnon, J.
Partner: UNT Libraries Government Documents Department
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The Nitric Acid Dissolution of Uranium-Aluminum Alloy in a Flooded Continuous Dissolver

Description: Extensive pilot plant studies of the mercury-catalyzed nitric acid dissolution of unirradiated 7.5% uranium--92.5% aluminum alloy slugs were carried out in tall-pipe, flooded, continuous dissolvers
Date: unknown
Creator: Boeglin, A. F.; Buckham, J. A.; Chajson, L.; Lemon, R. B.; Paige, D. M. & Stoops, C. E.
Partner: UNT Libraries Government Documents Department
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Laboratory Studies on the Filtration of MTR Dissolver Solutions

Description: The objectives of this investigation were to determine if the MTR dissolver solutions can be filtered in a laboratory scale equipment simulating plant equipment and conditions, determine conditions during dissolving produce solutions of poor filtrability, determine what flowsheet or process modifications would be necessary to achieve acceptable filtration rates and determine how the percentage of insolubles in a dissolver solution influences the filtration rate.
Date: unknown
Creator: Cederberg, G. K.
Partner: UNT Libraries Government Documents Department
open access

ABWR: PL-2 Design Report

Description: From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date: October 15, 1960
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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The Engineering Climatology of the National Reactor Testing Station

Description: This is the second in a series of three climatological reports on the National Reactor Testing Station. This report presents, in a form useful to designers and engineers, data on the following subjects: temperature, mositure content of the air, precipitation, winds, state of the ground, dust and human comfort. The reasons for any significant variations in the observed parameters are discussed.
Date: unknown
Creator: De Marrais, G. A.
Partner: UNT Libraries Government Documents Department
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Workbook in Atmospheric Diffusion Calculations

Description: This workbook was prepared in response to numerous inquiries about the practical applications of the material in "Meteorology and Atomic Energy." Although designed primarily for use at the National Reactor Testing Station, the application of the material is not restricted to that location. The most frequently used equations and nomograms are demonstrated.
Date: unknown
Creator: De Marrais, G. A.
Partner: UNT Libraries Government Documents Department
open access

The Climatology of the National Reactor Testing Station

Description: This is the first in a series of three climatological reports on the National Reactor Testing Staton; those that follow will be the Engineering Climatology and Diffusion Climatology. This report is concerned with the general climatology of the area with particular emphasis on temperature, relative humidity, precipitation, snowfall, winds, pressure and special phenomena. The reasons for any significant variations in the observed meteorological parameters are discussed.
Date: unknown
Creator: DeMarrais, Gera;d A.
Partner: UNT Libraries Government Documents Department
open access

Diffusion Climatology of the National Reactor Testing Station

Description: This is the final in a series of three climatological reports on the National Reactor Testing Station. This report presents the results of the observational program conducted by the Weather Bureau that are pertinent to the study of atmospheric diffusion. Specialized diffusion investigations conducted are described. Data for diffusion climatology and diffusion measurements using radioactive and non-radioactive tracers are included.
Date: unknown
Creator: DeMarrais, Gerard A. & Islitzer, Norman F.
Partner: UNT Libraries Government Documents Department
open access

Preliminary Report on the Use of the Consolidated Engineering Corporation Mass Spectrometer Model 21-120 for the Isotopic Assay of Uranium

Description: Data obtained in the isotopic assay of enriched uranium samples using a Consolidated Engineering mass spectrometer, Model 21-120, are reported and compared with other values.
Date: unknown
Creator: Duffy, Wayne Edward; Heaton, K. M. & Francal, R. J.
Partner: UNT Libraries Government Documents Department
open access

Determination of Radium 226 in Mill Effluents

Description: Recent attempts at the Laboratory in determining radium-226 in effluents from mills engaged in processing uranium ores several significant sources of error were discovered that had not been previously known. In order to make this information available to interested parties at the earliest possible time, a brief description is provided.
Date: unknown
Creator: Ebersole, Earl R.; Harbertso, Alan; Flygare, J. Kenneth, Jr. & Sill, Claude W.
Partner: UNT Libraries Government Documents Department
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