Clinch River breeder reactor sodium fire protection system design and development

Conference · Fri Apr 13 00:00:00 EST 1984

OSTI ID:5048071

Foster, K W; Boasso, C J; Kaushal, N N

To assure the protection of the public and plant equipment, improbable accidents were hypothesized to form the basis for the design of safety systems. One such accident is the postulated failure of the Intermediate Heat Transfer System (IHTS) piping within the Steam Generator Building (SGB), resulting in a large-scale sodium fire. This paper discusses the design and development of plant features to reduce the consequences of the accident to acceptable levels. Additional design solutions were made to mitigate the sodium spray contribution to the accident scenario. Sodium spill tests demonstrated that large sodium leaks can be safely controlled in a sodium-cooled nuclear power plant.

• Research Organization: Rockwell International Corp., Canoga Park, CA (USA). Energy Systems Group; Clinch River Breeder Reactor Plant Project Office, Oak Ridge, TN (USA)
• DOE Contract Number: AT03-76SF76026
• OSTI ID: 5048071
• Report Number(s): CONF-840411-18; ON: DE84008918
• Resource Relation: Conference: 3. meeting on liquid metal in energy applications, Oxford, UK, 9 Apr 1984; Other Information: Microfiche only, copy does not permit paper copy reproduction
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CLINCH RIVER BREEDER REACTOR
REACTOR PROTECTION SYSTEMS
BUILDINGS
FIRES
LEAKS
SODIUM
STEAM GENERATORS
ALKALI METALS
BOILERS
BREEDER REACTORS
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
POWER REACTORS
REACTORS
SODIUM COOLED REACTORS
VAPOR GENERATORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding