1971
DOI: 10.2172/4021262
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Optimization of a Shield for a Heat-Pipe-Cooled Fast Reactor Designed as a Nuclear Electric Space Power Plant.

Abstract: 'A reactor shield optimization procedure based on the ASOP shield optimization computer code and the DOT radiation transport code was used to determine a minimum-weight shield for a small fast reactor designed for a space nuclear electric power plant. The reactor, cylindrical in shape, is fueled with uranium nitride and cooled by potassium circulating through a matrix of stainless steel heat pipes embedded in the core; the design power is 450 kWt. The surrounding shield is typically asymmetric, having the over… Show more

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Cited by 3 publications
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“…For liquid metal cooled reactors, shield masses were estimated using ALKASYS-PC logic, which is based on Carlson (1985), Engle (1971), and Robinson (1996). For gas-cooled reactors, shield masses were scaled from the Enabler NERVA Derivative design.…”
Section: Approachmentioning
confidence: 99%
“…For liquid metal cooled reactors, shield masses were estimated using ALKASYS-PC logic, which is based on Carlson (1985), Engle (1971), and Robinson (1996). For gas-cooled reactors, shield masses were scaled from the Enabler NERVA Derivative design.…”
Section: Approachmentioning
confidence: 99%