PRISM: A Safe, Economic, and Testable Liquid-Metal Fast Breeder Reactor Plant

Autor: Robert C. Berglund, L.N. Salerno, Frank E. Tippets
Rok vydání: 1989
Předmět:
Zdroj: Nuclear Technology. 86:22-29
ISSN: 1943-7471
0029-5450
DOI: 10.13182/nt89-a34277
Popis: The Power Reactor Inherently Safe Module program is under U.S. Department of Energy sponsorship to develop a conceptual design for an advanced sodium-cooled liquid-metal reactor plant. This design is intended to provide significant reductions in plant construction and operating costs and reduced risk of construction delays while improving the already excellent level of plant safety achieved by the nuclear power industry. Design safety features are being developed that use inherent characteristics to passively respond to accident situations with high reliability and independence from human operator action.
Databáze: OpenAIRE