UNT Libraries Government Documents Department - 67 Matching Results

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Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

Date: February 15, 1960

Creator: Aerojet-General Corporation

Item Type: Report

open access

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

Date: July 31, 1960

Creator: Aerojet-General Corporation

Item Type: Report

open access

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

Date: February 22, 1961

Creator: Aerojet-General Corporation

Item Type: Report

open access

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961

Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations.

Date: August 10, 1961

Creator: Aerojet-General Corporation

Item Type: Report

open access

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.

Date: August 17, 1962

Creator: Aerojet-General Corporation

Item Type: Report

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Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

Date: November 15, 1963

Creator: Aerojet-General Corporation

Item Type: Report

open access

Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1963

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

Date: February 15, 1963

Creator: Aerojet-General Corporation

Item Type: Report

open access

Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1964

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

Date: November 13, 1964

Creator: Aerojet-General Corporation

Item Type: Report

open access

Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1964

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

Date: February 15, 1965

Creator: Aerojet-General Corporation

Item Type: Report

open access

Full Power and Limited Endurance Test of the ML-1 Nuclear Power Plant (ANSOP 16625A)

Report presenting "[t]he results of performance analyses of the ML-1 nuclear power plant based on the test data obtained during ANSOP 16625A" (p. v).

Date: September 1964

Creator: Aerojet-General Corporation

Item Type: Report

open access

Design for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor

The purpose of this document is to present criteria for the Titles I and II design of the Fast Flux Loop Facility which is to be a part of the Advanced Test Reactor. This facility is to be used for irradiation of fast reactor assemblies under simulated fast reactor operating conditions.

Date: July 1962

Creator: Babcock & Wilcox Company. Atomic Energy Division.

Item Type: Report

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Transportability Studies : ML-1 Nuclear Power Plant

Report that discusses programs to determine the transportability of the ML-1 nuclear power plant via railroad, tractor-trailer, and aircraft.

Date: April 1960

Creator: Blakley, J. W.; Alcorn, J. S.; Del Valle, L. G.; Healy, P. W.; Moran, D. H. & Scott, W. S.

Item Type: Report

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.

Item Type: Report

open access

In-Pile Test of Prototype ML-1 Fuel Elements

Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.

Date: June 1964

Creator: Brunhouse, J. S.; Burgess, A. B.; Geering, G. T.; Nakazato, S. & Titus, G. W.

Item Type: Report

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.

Item Type: Report

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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.

Item Type: Report

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.

Item Type: Report

open access

Completion Report for Observation Wells 1 through 49, 51, 54, 55, 56, 80, and 81 at the National Reactor Testing Station, Idaho

From introduction: "This report presents lithologic and geophysical logs and construction data for NRTS research observation wells."

Date: May 1964

Creator: Chase, G. H.; Teasdale, Warren E.; Ralston, D. A. & Jensen, Rodger G.

Item Type: Report

open access

Final Summary Report of the Gas-Cooled Reactor Experiment-1

Report describing the Gas-Cooled Reactor test facility, its ongoing testing and evaluations of a test reactor, and its operating conditions and characteristics.

Date: October 1963

Creator: Chesworth, R. H.

Item Type: Report

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Radiological Aspects of SNAPTRAN 2/10A-3 Destructive Test

From abstract: "This report describes in detail an extensive monitoring grid used to monitor the radiological effects of the destructive excursion and subsequent release of fission products."

Date: January 1965

Creator: Cordes, O. L.; Bird, R. P.; Dinneen, G. A. & Fielding, J. R.

Item Type: Report

open access

Routine Testing and Calibration Procedures for Multichannel Pulse Analyzers and Gamma-Ray Spectrometers

Report describing the results of laboratory tests with procedures for calibration of equipment and performance requirements.

Date: November 1, 1963

Creator: Crouch, D. F. & Heath, R. L.

Item Type: Report

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Summary Report of Design Criteria for a Thermal Flux Liquid Metal Package Loop in the Advanced Test Reactor

From introduction: "Report summarizing all work completed during the preparation of design criteria for thermal flux loop."

Date: March 1963

Creator: Ebasco Services Incorporated

Item Type: Report

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Post-Test Physical, Chemical and Metallurgical Analysis of SNAPTRAN-3 Fuel

The fuel element damage which occurred during the SNAPTRAN-3 Destructive Test of a Snap 10A/2 reactor is described. Chemical analysis of the fuel indicated that approximately 15% of the hydrogen was released and that the core flux was higher toward the center both radially and axially. Metallurgical analysis of the fuel determined the presence of the epsilon, delta, and gamma phases in the grain structure and evidence of a possible alpha or beta phase.

Date: June 1965

Creator: Fletcher, R. D.

Item Type: Report

open access

Annual Progress Report on Fuel Element Development for Fiscal Year 1961

Report that reviews the yearly progress made in Reactor Fuel and Materials Development Program at the Engineering Test Reactor (ETR) and Materials testing reactor (MTR).

Date: March 9, 1962

Creator: Gibson, G. W. & Shupe, O. K.

Item Type: Report

UNT Libraries Government Documents Department - 67 Matching Results

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Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962

Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963

Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1963

Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1964

Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1964

Full Power and Limited Endurance Test of the ML-1 Nuclear Power Plant (ANSOP 16625A)

Design for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor

Transportability Studies : ML-1 Nuclear Power Plant

Zirconium Processing Capability of the Idaho Chemical Processing Plant

In-Pile Test of Prototype ML-1 Fuel Elements

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

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

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

Completion Report for Observation Wells 1 through 49, 51, 54, 55, 56, 80, and 81 at the National Reactor Testing Station, Idaho

Final Summary Report of the Gas-Cooled Reactor Experiment-1

Radiological Aspects of SNAPTRAN 2/10A-3 Destructive Test

Routine Testing and Calibration Procedures for Multichannel Pulse Analyzers and Gamma-Ray Spectrometers

Summary Report of Design Criteria for a Thermal Flux Liquid Metal Package Loop in the Advanced Test Reactor

Post-Test Physical, Chemical and Metallurgical Analysis of SNAPTRAN-3 Fuel

Annual Progress Report on Fuel Element Development for Fiscal Year 1961