Special Welding Techniques : Final Summary Report (open access)

Special Welding Techniques : Final Summary Report

From foreword: This is the final report on Special Welding Techniques. The work of the third and final year is discussed in detail, and the accomplishments of the first two years are summarized.
Date: January 1957
Creator: Mueller, John; Maxwell, William & Siltanen, James
System: The UNT Digital Library
Development of Iron-Aluminum Base Alloys for Gas Cooled Reactor Components: Second Quarterly Progress Report, June 1958 (open access)

Development of Iron-Aluminum Base Alloys for Gas Cooled Reactor Components: Second Quarterly Progress Report, June 1958

From summary: Description of a program undertaken to develop an iron-aluminum base alloy for service approaching 1600 degrees Fahrenheit. The program includes development of an alloy, development of techniques for fabricating fuel elements, reprocessing investigations and irradiation testing of iron-aluminum base alloys.
Date: June 1958
Creator: Mueller, J.
System: The UNT Digital Library
Fluidized Bed Reactor Study: Phase I - Feasibility (open access)

Fluidized Bed Reactor Study: Phase I - Feasibility

From abstract: The Fluidized Bed Reactor (FBR) consists of a bed of fuel pellets which circulate in a confined core region as the result of the upward flow of fluid through the particles. In the present concept the fluid acts as a fluidizing, coolant and reactor moderator medium. This report is the results of the Phase I study to determine the feasibility of this concept.
Date: February 1959
Creator: unknown
System: The UNT Digital Library
Development of Iron-Aluminum Base Alloy for Gas Cooled Reactor Components: Final Report (open access)

Development of Iron-Aluminum Base Alloy for Gas Cooled Reactor Components: Final Report

From summary: Description of an iron-aluminum-chromium alloy, DB-2, used as the starting point of a program initiated to develop an iron-aluminum base alloy for cladding gas-cooled reactor core components. Secondary aims were to gain knowledge of fuel element fabric-ability, radiation effects and acid solubility of iron-aluminum base alloys.
Date: April 1959
Creator: Tate, Frank
System: The UNT Digital Library
ANPP Code Development Program Pressurized Water Task Quarterly Progress Report: Number One, November 1959 (open access)

ANPP Code Development Program Pressurized Water Task Quarterly Progress Report: Number One, November 1959

From introduction: The objective of this program is the development of a nuclear physical model and its calculation code for pressurized-water cooled and moderated reactors to predict accurately reactivity, rod positions and power distributions at operating temperatures, and reactor life from a nuclear standpoint.
Date: November 1959
Creator: Olsen, T. M.; Welshans, L. & Eicheldinger, C.
System: The UNT Digital Library