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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
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
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