ALPR Preliminary Design Study (Argonne Low Power Reactor) Phase 1 (open access)

ALPR Preliminary Design Study (Argonne Low Power Reactor) Phase 1

A preliminary design study, Phase I of the ALPR project, has been made in accordance with the Army Reactors Branch specifications for a nuclear "package" power plant with a 200-260-kw electric and 400 kw heating capacity. The plant is to be installed at the Idaho Reactor Testing Station as a prototype for remote arctic installations. The "conventional" power plant as well as the exterior reactor components are described in the accompanying report and cost estimate by Pioneer Service and Engineering Company, Architect-Engineers for the project."Nuclear" components of the reactor are designed by Argonne National Laboratory as described in the present report.
Date: April 20, 1956
Creator: Treshow, M.; Pearlman, H.; Rossin, D. & Shaftman, D.
System: The UNT Digital Library
The Manufacture Of Enriched Uranium Fuel Slugs for the Experimental Breeder Reactor (open access)

The Manufacture Of Enriched Uranium Fuel Slugs for the Experimental Breeder Reactor

This report describes the specifications, materials and the sequence of operations used to found and fabricate the first charge of enriched uranium fuel in the Experimental Breeder Reactor.
Date: April 20, 1953
Creator: Shuck, Arthur B., 1918-
System: The UNT Digital Library
Progress Report on the Experimental Breeder Reactor April 1, 1951 Through January 31, 1953 (open access)

Progress Report on the Experimental Breeder Reactor April 1, 1951 Through January 31, 1953

This report describes the progress on the experimental breeder reactor. It focuses on the approach to critical experiments, calibration of controls and flues and flux distributions.
Date: February 20, 1953
Creator: Lichtenberger, H. V.; Novick, M.; Cerutti, B. C.; Cameron, R. A.; McGinnis, D. F.; Pettitt, E. N. et al.
System: The UNT Digital Library
Techniques for X-Ray Examinations of End-Weld Closures and Can-to-Cap Brazes on CP-6 Type Fuel Elements : Final Report -- Metallurgy Program 7.7.7 (open access)

Techniques for X-Ray Examinations of End-Weld Closures and Can-to-Cap Brazes on CP-6 Type Fuel Elements : Final Report -- Metallurgy Program 7.7.7

A fuel element assembly in which a uranium slug is bonded to an impact extruded aluminum can by means of aluminum-silicon eutectic, and in which the can is capped with a thin aluminum disc, brazed and welded to the can, may contain,(a) imperfections common to brazed and welded metal sections, and (b) inhomogeneities arising from oxidation of uranium, and alloy formation between uranium, aluminum and silicon.
Date: January 20, 1954
Creator: Sidhu, S. S.
System: The UNT Digital Library