Quarterly Progress Report on Reactor Development 400 Program (open access)

Quarterly Progress Report on Reactor Development 400 Program

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, (2) change the power distribution in the core, and (3) change the amount of reactivity corresponding to a given stream volume in the core. The physics calculations show that uncertainties in critical mass are adequately covered by the number and variety of fuel assemblies and that the possible changes in core characteristics with the different fuel assemblies should provide valuable information about the factors affecting maximum power density and stability in a boiling water reactor.
Date: April 30, 1956
Creator: Stuart McLain & Members of the Laboratory Staff
System: The UNT Digital Library
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
Reactor Engineering Division Quarterly Report [for] October, November, December 1955. Section I (open access)

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

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 was, therefore, accepted. General construction work by the Sumner Sollitt Company on the remainder of the plant has begun.
Date: April 1956
Creator: Members of the Reactor Engineering Division
System: The UNT Digital Library