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The Disposal of Radioactive Wastes (open access)

The Disposal of Radioactive Wastes

Technical report describing a brief survey of the problems concerned with radioactive waste disposal.
Date: June 19, 1955
Creator: Ophel, Ivan L.
System: The UNT Digital Library
Proceedings of the Sixth Tripartite Instrumentation Conference, Part 3: System and Component Reliability (open access)

Proceedings of the Sixth Tripartite Instrumentation Conference, Part 3: System and Component Reliability

Collection of papers presented during the third session (Tuesday, April 21, 1959) at the 6th Tripartite Instrumentation Conference. The five papers describe reliability, maintenance, and failure of electronic equipment and other components in reactors at Chalk River (Canada), Harwell (U.K.), and Oak Ridge (U.S.).
Date: June 1959
Creator: Woolston, J. E. & Townsend, S. J.
System: The UNT Digital Library
Reactor Grade Zircaloy-2 Ingot (open access)

Reactor Grade Zircaloy-2 Ingot

Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-2, and intended for the production of reactor components.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-2 Wire Material (open access)

Zircaloy-2 Wire Material

Scope. This specification covers Zircaloy-2 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-2 Tubing for Fuel Sheathing (open access)

Zircaloy-2 Tubing for Fuel Sheathing

Scope. This specification covers Zircaloy-2 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures ae required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-2 Sheet and Strip Material (open access)

Zircaloy-2 Sheet and Strip Material

Scope. This specification covers Zircalogy-2 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are quired.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Reactor-Grade Zircaloy-4 Ingot (open access)

Reactor-Grade Zircaloy-4 Ingot

Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-4, and intended for the production of reactor components.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-4 Wire Material (open access)

Zircaloy-4 Wire Material

Scope. This specification covers Zircaloy-4 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library

Zircaloy-4 Tubing for Fuel Sheathing

Scope. This specification covers Zircaloy-4 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-4 Sheet and Strip Material (open access)

Zircaloy-4 Sheet and Strip Material

Scope. This specification covers Zircaloy-4 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library