Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960 (open access)

Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960

Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Date: February 3, 1961
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
System: The UNT Digital Library
Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968 (open access)

Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968

From Foreword: "Report containing information about ongoing research and development taking place in the Oak Ridge National Laboratory's Fuels and Materials Development Program. This includes a series of test reports covering such subjects as reactor fuels, the development of nitride fuels, and the effects of radiation on structural materials."
Date: February 1969
Creator: Oak Ridge National Laboratory. Metals and Ceramics Division.
System: The UNT Digital Library
Instrumentation and Controls Division Annual Progress Report, September 1, 1968 (open access)

Instrumentation and Controls Division Annual Progress Report, September 1, 1968

Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Date: February 1969
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
System: The UNT Digital Library
Design Analysis of a Prepackaged Nuclear Power Plant: Volume 1, Primary and Secondary System Design (open access)

Design Analysis of a Prepackaged Nuclear Power Plant: Volume 1, Primary and Secondary System Design

Design analysis of a prepackaged nuclear power plant.
Date: February 1, 1959
Creator: unknown
System: The UNT Digital Library
Design Analysis of a Prepackaged Nuclear Power Plant: Volume 2, Reactor Design Analysis (open access)

Design Analysis of a Prepackaged Nuclear Power Plant: Volume 2, Reactor Design Analysis

Design analysis of a prepackaged nuclear power plant.
Date: February 1, 1959
Creator: unknown
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis

Chemical engineering analysis and stress analysis for design of the 3 megawatt intermediate heat exchanger and steam generator for service with a liquid sodium heat transfer fluid.
Date: February 28, 1962
Creator: Alco Products (Firm)
System: The UNT Digital Library
A Low Cost Experimental Neutron Chain Reactor Part 2 (open access)

A Low Cost Experimental Neutron Chain Reactor Part 2

Description of cooling, shielding, controls are discussed for 100 kw and 1 Mw operation of a low cost experimental neutron chain reactor.
Date: February 5, 1954
Creator: Abernathy, Fred H.; Barrett, Lawrence G.; Berger, William A.; Dever, John A.; Maurer, John F.; Mesler, Russell B. et al.
System: The UNT Digital Library
Gas Pressurization of Homogeneous Reactor Test (open access)

Gas Pressurization of Homogeneous Reactor Test

Gas pressurization of homogeneous reactor test results.
Date: February 14, 1956
Creator: unknown
System: The UNT Digital Library
Process Waste Water Treatment Plant: Preliminary Report (open access)

Process Waste Water Treatment Plant: Preliminary Report

Preliminary report on waste water treatment plant to treat the low level radioactive liquid waste from the various laboratory processes.
Date: February 1957
Creator: unknown
System: The UNT Digital Library
Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1 (open access)

Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1

Report discussing the evaluation of the "behavior of austenitic and ferritic stainless steels, iron-chromium-aluminum base alloys and nickel-base superalloys, in medium and high temperature simulated reactor environments" (p. 2).
Date: February 1961
Creator: Pessl, H. J.
System: The UNT Digital Library
Plutonium Recycle Critical Facility: Final Safeguards Analysis (open access)

Plutonium Recycle Critical Facility: Final Safeguards Analysis

Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.
Date: February 1962
Creator: Anderson, J. K. & Winegardner, W. K.
System: The UNT Digital Library
Preliminary Investigations for an Advanced Engineering Test Reactor (open access)

Preliminary Investigations for an Advanced Engineering Test Reactor

Study carried out to determine a suitable reactor system or systems for the testing of water, gas, and liquid-metal cooled fuel assemblies.
Date: February 22, 1957
Creator: Elgert, O. J.; Leyse, C. F. & Ott, D. G.
System: The UNT Digital Library
Critical Mass Studies of Plutonium Solutions (open access)

Critical Mass Studies of Plutonium Solutions

Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date: February 15, 1960
Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
System: The UNT Digital Library
Army Package Power Reactor APPR-1 Operating Manual and Inspection and Service Manual (open access)

Army Package Power Reactor APPR-1 Operating Manual and Inspection and Service Manual

Report containing basic operating instructions for the operation of the Army Package Power Reactor. This includes descriptions of the the plant's systems, operations, and safety procedures.
Date: February 1958
Creator: Alco Products (Firm)
System: The UNT Digital Library
Advanced Test Reactor Servo Regulator Rod Test Program (open access)

Advanced Test Reactor Servo Regulator Rod Test Program

From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."
Date: February 1964
Creator: Pickett, R. T., III
System: The UNT Digital Library
Salt Bath Heat Transfer Rates for Uranium Plate (open access)

Salt Bath Heat Transfer Rates for Uranium Plate

Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
Date: February 1, 1962
Creator: Burditt, R. B.
System: The UNT Digital Library
Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel (open access)

Static Tests of Corrosion Inhibitors for Aluminum and Carbon Steel

The experiments described in this report were performed for two purposes: (1) to find a chemical, or combination of chemicals, that would be effective for inhibiting corrosion of steel in static portions of the Hanford water systems, and (2) as screening tests to select candidate mixtures for further testing to replace sodium dichromate as the inhibitor of aluminum and steel corrosion in the Hanford single-pass reactor cooling water.
Date: February 1965
Creator: Richman, R. B.
System: The UNT Digital Library
The Liquid Metal Thorium Breeder Reactor (open access)

The Liquid Metal Thorium Breeder Reactor

From introduction: "Investigation of breeding potential and technical and economic feasibility of breeding in the Liquid Metal Fuel Reactor concept."
Date: February 1960
Creator: unknown
System: The UNT Digital Library
Results of Air-Water and Steam-Water Tests on Radial Vane Steam Separator Models (open access)

Results of Air-Water and Steam-Water Tests on Radial Vane Steam Separator Models

From introduction: "Describes progress in the development of radial vane primary separators following initial work reported in GEAP 3564."
Date: February 1962
Creator: Riesland, J. I.
System: The UNT Digital Library
Conceptual Design for 75 MWe Mixed Spectrum Superheating Reactor Power Plant (open access)

Conceptual Design for 75 MWe Mixed Spectrum Superheating Reactor Power Plant

"This report presents the conceptual design of a 75 MWe prototype Mixed Spectrum Superheater power plant. The scope of the work has emphasized primarily the design, performance, and cost information on the nuclear portion of the plant. The research and development programs required to insure plant feasibility are also present."--Intro.
Date: February 25, 1962
Creator: U.S. Atomic Energy Commission
System: The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1 (open access)

1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1

From introduction: "Summary report of the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company."
Date: February 14, 1964
Creator: General Electric Company
System: The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2 (open access)

1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2

From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source."
Date: February 14, 1964
Creator: General Electric Company
System: The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3 (open access)

1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3

From introduction: "Contains the appendices and a complete set of drawings related to the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company for the United States Atomic Energy Commission."
Date: February 14, 1964
Creator: General Electric Company
System: The UNT Digital Library
Methods, System Optimization, and Safety Studies for a 1000 MegaWatt Sodium-Cooled Fast Reactor: Task 3 and 5 report of 1000 MegaWatt Liquid Metal Fast Breeder Reactor Follow-On Work (open access)

Methods, System Optimization, and Safety Studies for a 1000 MegaWatt Sodium-Cooled Fast Reactor: Task 3 and 5 report of 1000 MegaWatt Liquid Metal Fast Breeder Reactor Follow-On Work

From introduction: "Evaluation of trade-off and optimization studies in which numerous design parameters and economic ground-rules are varied to determine the effect on the economics of the reference concept. Selected safety studies."
Date: February 1969
Creator: General Electric Company
System: The UNT Digital Library