Effects of thermocouple installation and location on fuel rod temperature measurements
Creators
- 1. Idaho National Engineering Lab., EG and G Idaho, Inc., P.O. Box 1625, Idaho Falls, ID 83415
Description
This paper describes the results of analyses of nuclear fuel rod cladding temperature data obtained during in-reactor experiments under steady state and transient (simulated loss-of-coolant accident) operating conditions. The objective of the analyses was to determine the effect of thermocouple attachment method and location on measured thermal response. The use of external thermocouples increased the time to critical heat flux (CHF), reduced the blowdown peak temperature, and enhanced rod quench. A comparison of laser welded and resistance welded external thermocouple responses showed that the laser welding technique reduced the indicted cladding steady state temperatures and provided shorter time-to-CHF. A comparison of internal welded and embedded thermocouples indicated that the welded technique gave generally unsatisfactory cladding temperature measurements. The embedded thermocouple gave good, consistent results, but was possibly more fragile than the welded thermocouples. Detailed descriptions of the thermocouple designs, attachment methods and locations, and test conditions are provided
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- LaGrange Park, IL (USA)
- ISBN
- 0-89448-110-X
- Imprint Title
- Thermal hydraulics of nuclear reactors
- Journal Page Range
- p. 1483-1490.
Conference
- Title
- 2. international topical meeting on nuclear reactor thermal hydraulics (ANS).
- Dates
- 11-13 Jan 1983.
- Place
- Santa Barbara, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17089972
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BLOWDOWN; COMPARATIVE EVALUATIONS; CRITICAL HEAT FLUX; DATA PROCESSING; FUEL CANS; FUEL RODS; FUEL-CLADDING INTERACTIONS; LASER WELDING; LOSS OF COOLANT; NUCLEAR POWER PLANTS; PERFORMANCE TESTING; QUENCHING; RESISTANCE WELDING; SPECIFICATIONS; STEADY-STATE CONDITIONS; TEMPERATURE CONTROL; TEMPERATURE MEASUREMENT; THERMOCOUPLES; TIME DEPENDENCE; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; CONTROL; EVALUATION; FABRICATION; FUEL ELEMENTS; HEAT FLUX; HEAT TREATMENTS; JOINING; MEASURING INSTRUMENTS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; TESTING; THERMAL POWER PLANTS; WELDING