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Proposal for an Advanced Engineering Test Reactor : ETR II

Description: Report containing "the results of a study which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR or in existing commercial test reactors" (p. 5).
Date: March 17, 1960
Creator: deBoisblanc, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MUFT Revision : A Fast Neutron Spectrum Code for the IBM-650

Description: Report documenting the MUFT-R program, which is "designed to solve the fast neutron transport problem for general mixtures of elements and obtain sets of average fast neutron diffusion constants for specified portions of the fast energy spectrum" (p. iii). Includes detailed derivations of utilized equations.
Date: 1962
Creator: Grimesey, Robert A.; Mullen, Frank Edward & Gannon, L. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Supplement to Standard Practices for Design of MTR and ETR Safety Circuits

Description: Report that offers updated information from the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) "experiment safety circuit manual by providing ETR power reduction curves and other information on ETR not yet available at the time the manual was issued, September 15, 1957" (p. 1).
Date: November 21, 1958
Creator: Jones, L. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO

Description: Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects.
Date: August 23, 1956
Creator: Andelin, Robert L.; Anderson, Edward L. & McVey, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Pilot Plant Development Studies of a Continuous Process for Recovering Uranium from Nichrome Fuels

Description: Report documenting a process for recovering uranium from nichrome fuels (HTRE). This is accomplished by dissipating the fuel into a mixture of HCl-HNO3, stripping away chlorine ions with HN03, and recovering the uranium via tributyl phosphate solvent extraction.
Date: June 20, 1962
Creator: Chamberlain, H. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ICPP Waste Calcining Facility : Safety Analysis Report

Description: Report documenting a study "made of the radiological hazards associated with operation of the ICPP Waste Calcination Facility" and contains "[d]etails of the safety analysis and extensive information on the process, equipment, and operation procedures" (p. iii). Each section has its own pagination.
Date: December 1, 1963
Creator: Lakey, L. T. & Bower, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Summary of the Spert-I, -II, and -III reactor facilities

Description: Report containing "[a] brief description and design data summary of each of the SPERT Reactor Facilities is presented. Engineering, operating, and physics data are tabulated for use as basic references" (p. 3)
Date: November 1, 1957
Creator: Montgomery, C. R.; Norberg, J. A. & Wilson, T. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Engineering Test Reactor Critical Facility Hazards Summary Report, Supplement I

Description: Report that "is a supplement to IDO-16332, "The Engineering Test Reactor Critical Facility Hazards Summary Report", presenting information on the conduct in the Facility of certain experiments which are expected to be operated in the Engineering Test Reactor" (p. 3).
Date: January 24, 1958
Creator: deBoisblanc, D. R.; Burdick, Earl E. & DeBoer, T. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Source Strength Information for Shielding and Stack Effluent Calculations: a Standard Practices Guide

Description: Report presenting the curves and methods used "for determining gross fission product gamma energy in Mev/sec-watt, gross fission product beta decay in curies/sec-watt, delayed uranium fission neutrons in neutrons/sec-watt and N16 and N17 decay in photons/sec-cc of water" (p. 1).
Date: October 3, 1958
Creator: Jones, L. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Standard Practices Guide for Writing Experimental Operating Manuals

Description: This is a sample operating manual designed to aid experimenters in writing operating manuals for MTR and ETR experiments. It contains what is felt to be the necessary information for operating a particular experiment. One of the main functions of an operating manual is to provide quick reference to material needed in an emergency. It is believed this type of manual provides the required information without an excessive amount of bulky, surplus material.
Date: December 15, 1958
Creator: Ford, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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