Effects of cladding surface thermocouples and electrical heater rod design on quench behavior

Technical Report · Wed Feb 01 04:00:00 EST 1984

OSTI ID:5054858

Gottula, R C

A separate effects experiment program was conducted on a bundle of nine electrical heater rods in the Loss-of-Fluid Test (LOFT) Test Support Facility (LTSF). The prototype cladding-embedded thermocouples did not function correctly during the experiment. Results indicate that (a) cladding external thermocouples had a negligible effect on the cooldown rate and the quench behavior of a cartridge-type heater rod under rapid (1 to 2 m/s) flooding conditions at high pressure, (b) cladding external thermocouples were selectively cooled during the quenching process and do not accurately measure cladding temperature during the part of the transient, and (c) the time-to-quench was significantly less for the cartridge-type heater rod than for the solid-type heater rod. The cartridge-type heater rod has been shown to satisfactorily simulate the thermal response of a nuclear fuel rod through analytical and experimental data comparisons; therefore, the results from the cartridge-type heater rod are considered applicable to LOFT nuclear fuel rods.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5054858
• Report Number(s): NUREG/CR-2691; EGG-2186; ON: DE84010350
• Country of Publication: United States
• Language: English

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