In-reactor measurement of fuel element cladding temperatures

Technical Report · Fri Apr 08 04:00:00 EST 1960

DOI:https://doi.org/10.2172/10169652· OSTI ID:10169652

Doman, D R

A design was developed for leading thermocouples from a high-temperature, pressurized water reactor-coolant system of such integrity that no reactor shutdowns were caused by its use. Using this design, measurements of the fuel-element-cladding temperature and its variation with time were made in three tests on elements clad in type X-8001 aluminum alloy. The following conclusions were reached from the test results: (1) the cladding temperature of a fuel element operated at low heat flux in high bulk-outlet temperature water did not increase with time and was slightly lower than predicted by the Sieder-Tate equation; (2) cladding temperatures of fuel elements operated at high heat flux in either high bulk-inlet or outlet temperature water increased 40 C higher than predicted by the Sieder-Tate equation with initial temperatures equal to the predicted temperatures; and (3) the rate of temperature increase appeared dependent only on fuel-element heat flux and location with respect to the front and rear faces of the reactor.

• Research Organization: General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10169652
• Report Number(s): HW--61767; ON: DE94015691
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ALUMINIUM BASE ALLOYS
CORROSION
DESIGN
EXPERIMENTAL DATA
FUEL CANS
FUEL ELEMENTS
HANFORD PRODUCTION REACTORS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
TEMPERATURE MEASUREMENT
THERMOCOUPLES