Design of a Pilot Plant Facility for Radioactive Demonstration of the Pot Calcination Process (open access)

Design of a Pilot Plant Facility for Radioactive Demonstration of the Pot Calcination Process

Report regarding the process development work at the Oak Ridge National Laboratory, including project objectives, design considerations, descriptions of equipment, and estimated costs.
Date: December 14, 1962
Creator: Wheeler, B. R. & Buckham, James Andrew
Object Type: Report
System: The UNT Digital Library
Terminal Report : Conceptual Study of a System for Radioactive Demonstration of the Chop-Leach Process (open access)

Terminal Report : Conceptual Study of a System for Radioactive Demonstration of the Chop-Leach Process

Report that summarizes the design work of the radioactive chop-leach demonstration at the Idaho Chemical Processing Plant presented in two parts.
Date: 1963
Creator: Buckham, J. A.; P'Pool, R. S. & Pitkin, R. G.
Object Type: Report
System: The UNT Digital Library
Proposal for an Advanced Engineering Test Reactor : ETR II (open access)

Proposal for an Advanced Engineering Test Reactor : ETR II

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.
Object Type: Report
System: The UNT Digital Library
MUFT Revision : A Fast Neutron Spectrum Code for the IBM-650 (open access)

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

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.
Object Type: Report
System: The UNT Digital Library
Preliminary Design 55,000 KW Prototype Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office (open access)

Preliminary Design 55,000 KW Prototype Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office

Report describing the preliminary design of a 55,000 kW prototype of a natural uranium nuclear power plant for the United States Atomic Energy Commission. Testing of the design and potential requirements for operating the plant are included.
Date: April 1, 1958
Creator: Kaiser Engineers
Object Type: Report
System: The UNT Digital Library
Feasibility Study, 44,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optium Power Plant) for United States Atomic Energy Commission, Idaho Operations Office (open access)

Feasibility Study, 44,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optium Power Plant) for United States Atomic Energy Commission, Idaho Operations Office

Report that "contains a discussion of the feasibility study and cost estimates for a gas cooled, partial enriched uranium, graphite moderated power plant" (p. 3).
Date: April 1, 1958
Creator: Kaiser Engineers
Object Type: Report
System: The UNT Digital Library
Standard Practices for Design of MTR and ETR Safety Circuits (open access)

Standard Practices for Design of MTR and ETR Safety Circuits

Report containing notes for designing safety circuits for the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR).
Date: September 15, 1957
Creator: Jones, L. H.
Object Type: Report
System: The UNT Digital Library
Supplement to Standard Practices for Design of MTR and ETR Safety Circuits (open access)

Supplement to Standard Practices for Design of MTR and ETR Safety Circuits

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.
Object Type: Report
System: The UNT Digital Library
Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO (open access)

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

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.
Object Type: Report
System: The UNT Digital Library
Startup Operation of a Production Facility for Separating Barium-140 from MTR Fuel (open access)

Startup Operation of a Production Facility for Separating Barium-140 from MTR Fuel

Report describing "the startup operation of a batch production facility for separating and purifying barium-140 from short-cooled MTR fuel" (p. 3).
Date: September 1, 1957
Creator: Legler, Billy Mason; Fairbourne, S. F.; Kelly, P. N. & Robinson, R. A.
Object Type: Report
System: The UNT Digital Library
A Study of the Feasibility of a Small Scale Reprocessing Plant for the Dresden Nuclear Power Station (open access)

A Study of the Feasibility of a Small Scale Reprocessing Plant for the Dresden Nuclear Power Station

Report describing the design, feasibility, and economic concerns of a small-scale reprocessing plant.
Date: April 28, 1961
Creator: Schneider, H.; Fletcher, R. D.; Codding, J. W.; Bearden, R. G.; Erickson, E. E.; Horn, S. J. et al.
Object Type: Report
System: The UNT Digital Library
An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant (open access)

An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant

Report evaluating the technical and economic feasibility of four zirconium fuel processes: the present STR process, the modified Zirflex process, the barium fluozirconate process, and the sodium formate process.
Date: April 27, 1962
Creator: Burn, P.
Object Type: Report
System: The UNT Digital Library
Pilot Plant Development Studies of a Continuous Process for Recovering Uranium from Nichrome Fuels (open access)

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

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.
Object Type: Report
System: The UNT Digital Library
Critical Path Scheduling of ETR and MTR Reactor Shutdowns (open access)

Critical Path Scheduling of ETR and MTR Reactor Shutdowns

Report describing a method for planning shutdown projects and scheduling the manpower to shut down Materials Testing Reactors (MTR) and Engineering Test Reactors (ETR).
Date: January 10, 1962
Creator: Jacobs, R. T. & Myers, L. L.
Object Type: Report
System: The UNT Digital Library
Unitized Microfilm System for Engineering Drawings of Idaho Operations Office, USAEC and Its Contractors (open access)

Unitized Microfilm System for Engineering Drawings of Idaho Operations Office, USAEC and Its Contractors

Report that describes an engineering drawing microfilm system that was developed for the United States Atomic Energy Commission's Idaho Operations Office and its contractors at the National Reactor Testing Station.
Date: April 16, 1962
Creator: Masterson, Richard G.
Object Type: Report
System: The UNT Digital Library
ICPP Waste Calcining Facility : Safety Analysis Report (open access)

ICPP Waste Calcining Facility : Safety Analysis Report

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.
Object Type: Report
System: The UNT Digital Library
Zirconium Processing Capability of the Idaho Chemical Processing Plant (open access)

Zirconium Processing Capability of the Idaho Chemical Processing Plant

Report discussing a hydrofluoric acid dissolution process that allows the processing of zirconium- or Zircaloy-clad zirconium-uranium fuels.
Date: October 1964
Creator: Bower, J. R.
Object Type: Report
System: The UNT Digital Library
A Preliminary Report on the MTR Crystal Spectrometer (open access)

A Preliminary Report on the MTR Crystal Spectrometer

Report regarding the installation and testing of a neutron crystal spectrometer. This was part of a slide show presentation.
Date: April 25, 1955
Creator: Evans, J. E.
Object Type: Report
System: The UNT Digital Library
The Quantitative Techniques of Scintillation Spectrometry as Applied to the Calibration of Standard Sources (open access)

The Quantitative Techniques of Scintillation Spectrometry as Applied to the Calibration of Standard Sources

Report presenting "the determination of absolute gamma emission rates for monoenergetic gamma emitters using a single-channel scintillation spectrometer. Examples are given for Cr⁵¹, Cs¹³⁷, Nb⁹⁵, and Zn⁶⁵. Sources of error are discussed and steps being taken to improve the accuracy of the method are described" (p. 1).
Date: April 25, 1955
Creator: Heath, R. L. & Schroeder, F.
Object Type: Report
System: The UNT Digital Library
MTR Technical Branch Quarterly Report, Third Quarter (open access)

MTR Technical Branch Quarterly Report, Third Quarter

Quarterly report for the technical branch of the Materials Testing Reactor of Idaho. Includes current developments and experiments.
Date: November 1, 1956
Creator: Conner, W. P.
Object Type: Report
System: The UNT Digital Library
Chemical Processing Instrumentation and Control Research Program (open access)

Chemical Processing Instrumentation and Control Research Program

Report regarding the chemical processing instrumentation designs and problems at the Idaho Chemical Processing Plant.
Date: September 18, 1957
Creator: Schneider, Harry
Object Type: Report
System: The UNT Digital Library
Design Bases for ICPP Waste Calcination Facility (open access)

Design Bases for ICPP Waste Calcination Facility

Report regarding a waste calcination unit that "will convert the fission product-containing aluminum nitrate solutions" "to granular alumina and fission product oxides" (p. 5).
Date: January 16, 1959
Creator: MacQueen, D. K. & Stevens, J. I.
Object Type: Report
System: The UNT Digital Library
Research and Development Studies on Waste Storage Process (open access)

Research and Development Studies on Waste Storage Process

Report documenting "the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide" (p. 4).
Date: May 19, 1961
Creator: Ortner, M. H.; Anderson, C. J. & Campbell, P. F.
Object Type: Report
System: The UNT Digital Library
Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office (open access)

Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office

Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Object Type: Report
System: The UNT Digital Library