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  Partner: UNT Libraries Government Documents Department
 Decade: 1960-1969
 Collection: Technical Report Archive and Image Library
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 3, Concept IV System Description

1000-MWe LMFBR Follow-On Study, Task I Report: Volume 3, Concept IV System Description

Date: June 1967
Creator: Goulding, B. J.
Description: From introduction: "This report has been prepared in conjunction with the Liquid Metal Fast Breeder Reactor (LMFBR) Follow-On Study. It is the Concept II description of Task I as outlined by Argonne National Laboratory (ANL) in Appendix C of their Follow-On-Study Program."
Contributing Partner: UNT Libraries Government Documents Department
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 4, Concept III System Description

1000-MWe LMFBR Follow-On Study, Task I Report: Volume 4, Concept III System Description

Date: July 1967
Creator: Goulding, B. J.
Description: From introduction: "The third of four designs to be developed by Babcock & Wilcox (B&W), Concept III observes ground rules established under the LMFBR Follow-On Program and is based on the estimated state of technology in 1980."
Contributing Partner: UNT Libraries Government Documents Department
1000-MWe LMFBR Follow-On Study, Task I Report: Volume 5, Concept IV System Description

1000-MWe LMFBR Follow-On Study, Task I Report: Volume 5, Concept IV System Description

Date: August 1967
Creator: Goulding, B. J.
Description: From introduction: "The last of four designs to be developed by Babcock & Wilcox (B&W), Concept IV observes ground rules established under the LMFBR Follow-On Program and is based on the estimated state of technology in 1980."
Contributing Partner: UNT Libraries Government Documents Department
The 1958 He4 Scale of Temperatures: Part 1. Introduction, Part 2. Tables for the 1958 Temperature Scale

The 1958 He4 Scale of Temperatures: Part 1. Introduction, Part 2. Tables for the 1958 Temperature Scale

Date: June 17, 1960
Creator: Brickwedde, F. G. (Ferdinand Graft), 1903-; van Dijk, H.; Durieux, M.; Clement, J. R. & Logan, J. K.
Description: Report containing information regarding He4 vapor pressure measurement as of 1958, the recent history of the vapor pressure temperature scale, and a series of tables containing these measurements.
Contributing Partner: UNT Libraries Government Documents Department
6144-Channel Time-of-Flight Analyzer

6144-Channel Time-of-Flight Analyzer

Date: September 1964
Creator: Walker, R. A. & Russell, J. T.
Description: Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Contributing Partner: UNT Libraries Government Documents Department
630A Maritime Nuclear Steam Generator Scoping Study

630A Maritime Nuclear Steam Generator Scoping Study

Date: April 6, 1962
Creator: unknown
Description: From foreword: This report presents the results of a study of a nuclear steam generator which uses reactor technology during the aircraft nuclear propulsion program to produce superheated steam for marine propulsion.
Contributing Partner: UNT Libraries Government Documents Department
630A Maritime Nuclear Steam Generator: Status Report Number 1

630A Maritime Nuclear Steam Generator: Status Report Number 1

Date: September 12, 1963
Creator: unknown
Description: From foreword: The primary purpose of this document is to set forth the current status of the 630A Nuclear Steam Generator, under development for the U.S. AEC.
Contributing Partner: UNT Libraries Government Documents Department
Abscissas and Weights for Guassian Quadrature For N=2 to 100, and N-125, 150, 175, 200

Abscissas and Weights for Guassian Quadrature For N=2 to 100, and N-125, 150, 175, 200

Date: December 28, 1966
Creator: Love, Carl H.
Description: The abscissas and weights for Gaussian Quadrature of order N = 2 to 100,and N = 125, 150, 175, and 200 are given. The abscissas are given to twenty-four places and the error is estimated to be no more than 1 unit in the last place. The weights are given to twenty-three places and the error is estimated to be no more than 1 unit in the last place.
Contributing Partner: UNT Libraries Government Documents Department
Absorption-Multistage Flash Distillation Process

Absorption-Multistage Flash Distillation Process

Date: September 1963
Creator: Fluor-Singmaster & Breyer, Inc.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
ABWR Design and Development Quarterly Progress Report: July 1 - September 30, 1961

ABWR Design and Development Quarterly Progress Report: July 1 - September 30, 1961

Date: October 16, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Description: Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
Contributing Partner: UNT Libraries Government Documents Department
ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962

ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962

Date: April 15, 1962
Creator: Combustion Engineering, inc. Nuclear Division.
Description: Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
Contributing Partner: UNT Libraries Government Documents Department
Acceleration Due to Gravity at the National Bureau of Standards

Acceleration Due to Gravity at the National Bureau of Standards

Date: June 1968
Creator: Tate, Douglas Roy
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Acid-Base Behavior in Aprotic Organica Solvents

Acid-Base Behavior in Aprotic Organica Solvents

Date: August 1968
Creator: Davis, Marion Maclean
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Acoustic Flowmeter Prototype Evaluation Tests

Acoustic Flowmeter Prototype Evaluation Tests

Date: January 1968
Creator: Pickett, Ellis B.
Description: Summary: "Prototype tests of an acoustic flowmeter system were made in a 24-ftdiam power penstock at Oahe Dam to evaluate the system prior to permanent installation in the outlet works at Summersville Dam. Comparative discharge measurements included acoustic, penstock pressure-momentum (Gibson), turbine model test ratings, scroll-case pressure differential (Winter-Kennedy flowmeter), and surge tank volume changes. The acoustic flowmeter measurements were very consistent and many of the comparisons were within 1%. The location of the measuring section for a single-path acoustic flowmeter must be selected to give a known or measurable relation between the flow pattern of the whole section and that along the acoustic path" (p. xi).
Contributing Partner: UNT Libraries Government Documents Department
Addendum to Hazard Summary Report Experimental Breeder Reactor-II (EBR-II)

Addendum to Hazard Summary Report Experimental Breeder Reactor-II (EBR-II)

Date: June 1962
Creator: Koch, L. J.; Loewenstein, W. B. & Monson, H. O.
Description: Report containing hazard and safety information regarding the Experimental Breeder Reactor-II in Idaho.
Contributing Partner: UNT Libraries Government Documents Department
Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core

Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core

Date: February 1965
Creator: Miller, R. W.
Description: From abstract: "explain all important features pertaining to a new pulsed irradiation reactor, the Capsule Driver, Core, and to analyze the potential problems and hazards of operating this reactor in the existing Spert IV facility."
Contributing Partner: UNT Libraries Government Documents Department
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development

Date: April 1962
Creator: Combustion Engineering, inc. Nuclear Division.
Description: First part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. I-ii).
Contributing Partner: UNT Libraries Government Documents Department
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies

Date: March 1962
Creator: Combustion Engineering, inc. Nuclear Division.
Description: Second part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. II-i).
Contributing Partner: UNT Libraries Government Documents Department
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients

Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Description: Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Contributing Partner: UNT Libraries Government Documents Department
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps

Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Description: Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Contributing Partner: UNT Libraries Government Documents Department
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept

Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Description: Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Contributing Partner: UNT Libraries Government Documents Department
Advanced Pressurized Water Reactor Study [Part 1, Supplement]: Phase 2--A Report

Advanced Pressurized Water Reactor Study [Part 1, Supplement]: Phase 2--A Report

Date: February 1960
Creator: Stone and Webster Engineering Corporation
Description: ...
Contributing Partner: UNT Libraries Government Documents Department
An Advanced Sodium-Graphite Reactor Nuclear Power Plant

An Advanced Sodium-Graphite Reactor Nuclear Power Plant

Date: March 15, 1960
Creator: Churchill, J. R. & Renard, J.
Description: Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Contributing Partner: UNT Libraries Government Documents Department
Advanced Test Reactor Burnout Heat Transfer Tests

Advanced Test Reactor Burnout Heat Transfer Tests

Date: January 1964
Creator: Croft, M. W.
Description: From abstract: "Results of burnout test to determine the limiting heat flux in a simulated Advanced Test Reactor fuel element channel."
Contributing Partner: UNT Libraries Government Documents Department