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The Determination of Fluoride in Plutonium Metal by Thorium Titration

Description: Abstract: "A titrimetric method for the determination of fluoride in plutonium is reported. Prior to a steam distillation of the fluoride, the bulk of the plutonium is separated by precipitation of the sulfate. The fluoride in the distillate is titrated at a pH of 3.2 with 0.001 M thorium nitrate, using chrome azurol-S indicator. Applied to samples containing 1 to 15 parts per million fluoride, the recovery is 87% and the precision on the 95% confidence level is +/- 0.65 ppm."
Date: May 4, 1954
Creator: Ferguson, W. S. & Newell, D. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium Graphite Reactor, Quarterly Progress Report, June-August 1953

Description: "Engineering was continued on the development of sodium cooled, graphite moderated type reactors. General studies were carried out as well as studies specifically devoted to the following: a. full scale poser-only plant, b. thirty-mega watt pilot plant, the SGR, c. sodium reactor experiment, the SRE. This work consisted of theoretical analysis of various aspects of nuclear performance; economic investigations of different fuel element, cooling system and plant arrangements; and experimental i… more
Date: January 20, 1954
Creator: Inman, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium Graphite Reactor, Quarterly Progress Report, March-June 1954

Description: "The Atomic energy Commission has undertaken a development program to provide the technology needed for the evaluation and economic design of nuclear power plants. This program is to be carried out during the next five years at several national laboratories and industrial organizations. The Sodium Graphite Reactor (the SGR) is one of those to be investigated and experimentally tested as part of this 5-year effort. The program on the SGR is intended to expand our area of information coverin… more
Date: September 1, 1954
Creator: Siegel, Sidney & Inman, Guy M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Probability and Extent of a Fission Product Release From a Power Reactor

Description: Report discussing both the probability of having a reactor accident that would release fission products, as well as the probable extent of the release of the products. This information, along with the contents of the fission products themselves, are based on statistical analysis and educated guesses.
Date: February 4, 1956
Creator: Fleck, Joseph A., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PM-3A Nuclear Power Plant Secondary Shield Design

Description: "The design, analysis, and selection of system components for functions related to secondary shielding and associated auxiliary systems for the Antarctic PM-3A Nuclear Power Plant are described. Backfill material characteristics, shielding and activation analyses, heat transfer analysis, backfill cooling system, water exclusion and removal system, and instrumentation and control are discussed."
Date: September 1961
Creator: Siler, W C
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Safe Conditions For Applying Titanium In H.A.P.O Process Equipment

Description: A two and one-half year period of extreme caution where titanium and nitric acid are involved has passed since the occurrence of the last and most serious uncontrolled incident involving titanium and nitric acid. During this period controlled explosions involving titanium and nitric acid have been routinely reproduced, additional laboratory and pilot plant experience has been gained and successful industrial applications have been appraised. Based on laboratory data and the known industrial exp… more
Date: October 6, 1956
Creator: Smith, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reduction of Air Borne Contamination UO₃ Plant

Description: Gradual corrosion and mechanical wear of equipment over a period of years has affected the seals and gasketing of the electric pot calcining equipment in the 224-U Building Cell E to such an extent that the desirable vacuum cannot be maintained in the pots. Air contamination has been gradually increasing, and this, together with a lowering of the mask working limits, has made it necessary to require personnel to wear assault masks continuously. Indications are that, with the increased productio… more
Date: May 11, 1956
Creator: Ingalls, W. P. & Sanborn, K. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear Safety of Right Elliptic and Right Annular Cylinders

Description: Past experience has shown that the demand for increase separations plant capacity comes up very regularly. One of the variables which greatly affects plant capacity is cross-sectional area of the individual vessels. Larger areas permit greater flow rates as well as more space for the installation of heat transfer piping (shell and tube concentrators). Design considerations of the separations plants vessels have been based on both circular cylinder and slab geometries. A study has been made to d… more
Date: June 1, 1956
Creator: Ketzlach, Norman
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hazardous Materials - Redox Plant

Description: The Redox process uses or produces only a very few materials that are hazardous for reasons other than radioactivity. The conditions under which these materials become hazardous were carefully taken into consideration in the development of the process and design of the equipment. A considerable about of information on the hazardous properties of the process materials was obtained so that the pertinent material could be incorporated into the process specifications. Providing the equipment is ope… more
Date: May 22, 1956
Creator: Underwood, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Hazard Summary Report on the Boiling Experiment Reactor (BER)

Description: Experiments performed by the Laboratory with the Borax Reactor at the National Reactor Testing Station have demonstrated that a boiling reactor possesses inherent safety characteristics which have not previously been included in the estimation of reactor hazards. Other operating characteristics of Borax were also sufficiently attractive to justify the development of boiling reactors for package power and central station power plant applications. Accordingly, a proposal was made to the Atomic En… more
Date: May 1954
Creator: West, J. M.; Anderson, G. A.; Dietrich, J. R.; Harrer, Joseph M.; Jameson, A. S. & Untermyer, Samuel, 1912-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Effect of Departure from the Optimum Operating Conditions on the Production Cost of Electricity from Gas-Cooled Nuclear Power Plants

Description: The second partial differentials of the production cost equation are derived in a generalized and non-dimensional form in order to determine the effect on production cost of electricity from a gas-cooled nuclear power plant of departure from optimum operating conditions. Fuel element surface temperatures up to 650 degrees C, production costs up to 1d. (A)/kwh and reactor coolant temperature rises up to half the maximum surface temperature are included. The most significant parameter is the rati… more
Date: 1962
Creator: Binns, Ian M. & Pulley, O. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Basis for the Computation of the Energy Dependence of the Neutron Flux and Slowing Down Density in a Bare Reactor

Description: A method is described for the computation of the energy dependence of the neutron flux and slowing down density in a bare reactor to form the basis of a 7090 Fortran computer program for survey studies of power reactors. Allowance is made for resonance absorption and resonance fission, neutron thermalisation, fast neutron reactions including (n, 2n) and (n, n), and anisotropic elastic scattering.
Date: September 1963
Creator: Lawrence, B. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor: Design of the MMSR Primary Shield

Description: The purpose of this report is to describe the shielding calculations and techniques used in sizing the MMSR primary shield, the results obtained, and the resulting shield thicknesses. The present report covers many of the items scheduled for presentation in the final MMSR shield design report to be issued in November of 1958. The primary shield in the MMSR consists of the reflector, thermal shields, pressure vessel wall, a 33" water annulus and a layer of lead shielding at the exterior of the… more
Date: April 1958
Creator: Smith, W. R. & Turner, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Pressure Vessel Material Surveillance Program at the Garigliano Nuclear Power Plant

Description: Abstract: A materials exposure program has been established in the Garigliano Nuclear Power Plant to measure the effect of neutron irradiation and time at temperate on the mechanical properties of the reactor pressure vessel steel. Base metal specimens were made from portions of the pressure vessel steel, and weld heat-affected zone and weld metal samples were taken from a weldment made from the pressure vessel steel and simulating a pressure vessel circumferential weld since there are no longi… more
Date: March 1964
Creator: Brandt, F. A. & Kobsa, I. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Lynchburg Test Reactor: Critical Experiment, Hazard Evaluation

Description: This report summarizes the hazards associated with the operation of the Lynchburg Test Reactor (LTR) critical experiments. The LTR critical experiment program is outlined and the design of the experiment is described. The experiments will provide basic data to check two-dimensional calculational methods and provide information needed in the design of the LTR.
Date: November 1959
Creator: Engelder, T. C. & Schutt, P. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Lynchburg Test Reactor Summary Hazards Report

Description: The Babcock and Wilcox Company (B&W) proposes to construct and operate a Nuclear Test Reactor on the grounds of the Company's integrated nuclear facilities site, Mt. Athos, near Lynchburg, Virginia. This preliminary Summary Hazards Report present to the U.S. Atomic Energy Commission (AEC), Division of Licensing and Regulations, a description of the facility, the characteristics of the proposed site, and an evaluation of potential hazards to the area surrounding the site of operation.
Date: April 1960
Creator: Kulynych, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 4

Description: The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nucl… more
Date: October 1, 1963
Creator: Sorlie, T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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