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

Description: 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 Enginee… more
Date: April 20, 1956
Creator: Treshow, M.; Pearlman, H.; Rossin, D. & Shaftman, D.
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Interim Report: Faret Experimental Program

Description: From Introduction: "The Fast Reactor Test (FARET) program is part of the United States Fast Reactor Program directed toward the demonstration of breeder reactors essential to the long-range goal of utilizing fertile fuels. (1) With-in this program is the current thinking that the early construction and operation of two or three prototype nuclear power plants of the order of 250 Mw(e) will lead eventually to the construction of practical and economic full scale breeder reactors by the early 1980… more
Date: April 1963
Creator: Smaardyk, A.; Bump, T. R.; Handwerk, J. & Handwerk, J.
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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
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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
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