Transient overpower accident consequences in the FTR with partial carbide core loading

Conference · Thu Jan 01 04:00:00 EST 1981

OSTI ID:5274647

Nguyen, D H; Lee, M Y

Although the early carbide fuel tests in the Fast Test Reactor (FTR) are less than subassembly size, the long-term irradiation program provides for an eventual loading of up to 14 carbide subassemblies (S/As). This work compares the transient overpower (TOP) accident consequences of the FTR partial carbide core with the safety envelope established for the all-oxide base case, and documented in the FTR, Final Safety Analysis Report. The method of study combines the determination of cladding failure using the UNCLE-T code and the calculation of molten fuel ejection and its consequences, including reactivity feedbacks and power history using the MELT-IIIA code.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 5274647
• Report Number(s): HEDL-SA-2291; CONF-810606-106; ON: DE82009871
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
COMPUTER CALCULATIONS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENT FAILURE
LIQUID METAL COOLED REACTORS
PLUTONIUM CARBIDES
PLUTONIUM COMPOUNDS
REACTIVITY WORTHS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
STRESSES
TEST REACTORS
THERMAL STRESSES
TRANSIENT OVERPOWER ACCIDENTS
TRANSURANIUM COMPOUNDS
URANIUM CARBIDES
URANIUM COMPOUNDS