Consequences of pipe ruptures in metal fueled, liquid metal cooled reactors

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6818090

Dunn, F E

The capability to simulate pipe ruptures has recently been added to the SASSYS-1 LMR systems analysis code. Using this capability, the consequences of severe pipe ruptures in both loop-type and pool-type reactors using metal fuel were investigated. With metal fuel, if the control rods scram then either type of reactor can easily survive a complete double-ended break of a single pipe; although, as might be expected, the consequences are less severe for a pool-type reactor. A pool-type reactor can even survive a protected simultaneous breaking of all of its inlet pipes without boiling of the coolant or melting of the fuel or cladding. 2 refs., 16 figs., 1 tab.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6818090
• Report Number(s): CONF-900804-18; ON: DE90011096; TRN: 90-019992
• Resource Relation: Conference: International topical meeting on fast reactor safety, Snowbird, UT (USA), 12-16 Aug 1990
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
REACTOR COOLING SYSTEMS
PIPES
RUPTURES
COMPUTERIZED SIMULATION
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
REACTOR SAFETY
S CODES
SCRAM
ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SHUTDOWN
REACTORS
SAFETY
SHUTDOWNS
SIMULATION
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding