PRISM; A safe, economic, and testable liquid-metal fast breeder reactor plant

Journal Article · Sat Jul 01 04:00:00 EDT 1989 · Nuclear Technology; (USA)

OSTI ID:5382509

Berglund, R C; Tippets, F E; Salerno, L N ^[1]

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1. General Electric Co., San Jose, CA (USA). Nuclear Technology Dept.

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.

• OSTI ID: 5382509
• Journal Information: Nuclear Technology; (USA), Journal Name: Nuclear Technology; (USA) Vol. 86:1; ISSN NUTYB; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COST
DESIGN
EPITHERMAL REACTORS
FAST REACTORS
LIQUID METAL COOLED REACTORS
NATIONAL ORGANIZATIONS
OPERATING COST
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RELIABILITY
RESEARCH PROGRAMS
SAFETY
US DOE
US ORGANIZATIONS