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Quarterly Progress Report on Reactor Development 400 Program

Description: Physics calculations have been made for various combinations of the four types of fuel assemblies to be used in the EBWR core. Two thicknesses of plates, 0.205 in. and 0.274 in., including the two 0.020-in. cladding layers, are to be made of both natural U and U containing 1.44% U235. A total of 148 assemblies, 74 natural and 74 enriched, are to be fabricated with six identical plates each. Various configurations of these fuel assemblies will be used to (1) change the critical size of the core,… more
Date: April 30, 1956
Creator: Stuart McLain & Members of the Laboratory Staff
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Manufacture of Enriched ZPR-III Fuel Plates

Description: This report is essentially a procedural account of the fabrication of certain enriched ZPR-III fuel plates for use in the ANL fast critical experiments at Arco, Idaho. A total of 208.92 kilograms of fully enrich, unalloyed uranium was processed. Of this amount 202.74 kilograms was received in the form of Oak Ridge type reduction buttons and 6.18 kilograms as pressed-powder plates. The completed fabrication consisted of 720 rectangular fuel plates having the nominal dimensions 3in. x 2in. x 1/8i… more
Date: October 1956
Creator: Yaggee, Frank L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Engineering Division Quarterly Report Section I January, February, March. 1956

Description: Physical calculations have been performed for various combinations of the four types of fuel assemblies to be used in the EBWR core. Two thicknesses of plates (0.205 in. and 0.274 in., including two 0.020-in. cladding layers) are to be made of both natural uranium and uranium containing 1.44% U235. Any given fuel assembly contains six identical plates. A total of 148 assemblies, 74 natural and 74 enriched, are to be fabricated. Various configurations of these fuel assemblies can be used to (1) … more
Date: July 1956
Creator: Members of the Reactor Engineering Division
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Quarterly Report October, November and December, 1956

Description: Methods of producing extremely clean surfaces on rolled Zircaloy-2 strip have been investigated. It has been found that the finer abrasives, 400 mesh or finer, are more effective than coarse types because of their ability to penetrate pits and crevices more readily. Two such cleanings, with an intermediate 35 v/o HNO3-5 v/o HF pickle, resulted in a microscopically clean surface. Ultrasonic inspection of the EBWR fuel plates has been completed during this quarter. Approximately 95% of the plates… more
Date: December 31, 1956
Creator: Foote, Frank G.; Schumar, James F. & Chiswik, Haim H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Process Equipment and Protective Enclosures Designed for the Fuel Fabrication Facility: Facility #350

Description: Report issued by the Argonne National Laboratory discussing the design and construction of equipment for reactor fuels. As stated in the summary, "the report describes the development, prototype construction, methods of testing, and leak detection of a modular hood design to be used in housing equipment and processes for the Argonne National Laboratory Fuel Fabrication Facility" (p. 9). This report includes tables, illustrations, and photographs.
Date: January 1956
Creator: Shuck, A. B. & Mayfield, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Engineering Division Quarterly Report [for] October, November, December 1955. Section I

Description: The gastight steel building (400,000 cu ft) in which all radioactive components are to be housed has been completed by the Graver Tank Company. This structure was tested for strength at 18.75 psig (20% above design pressure) and then tested for leaks. No leaks were found in soap bubble testing of all welded seams. Continuous measurements of temperature and pressure over a ten-day period showed the leakage, if any, to be less than the 500 cu/ ft/day at 15 psig specified. The gastight cylinder wa… more
Date: April 1956
Creator: Members of the Reactor Engineering Division
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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