Theoretical characterization of a dual-purpose gamma thermometer
The local heat generation rate (LHGR) in a pressurized water reactor is typically inferred from measurements of the thermal neutron flux. However, since the thermal neutron flux exhibits a large amount of structure positionally within a PWR fuel assembly, an alternate instrument, the gamma thermometer (GT), has been proposed as a means of improving the LHGR inference. Since the gamma flux is related to the fission rate, and since the gamma flux exhibits very little structure within a fuel assembly, the use of a gamma-based LHGR detector could significantly improve the measurement accuracy. More recently, a further application of the gamma thermometry principle has been advanced: that of a fluid level indicator for in-core measurements. The results of a two-part study directed at establishing the feasibility of such a device, are the subject of this paper.
- Research Organization:
- Tennessee Univ., Knoxville (USA). Dept. of Nuclear Engineering; Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6436645
- Report Number(s):
- CONF-810606-51; ON: DE81023216
- Country of Publication:
- United States
- Language:
- English
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IN CORE INSTRUMENTS
LEVEL INDICATORS
MEASURING INSTRUMENTS
PERFORMANCE
POWER DISTRIBUTION
PWR TYPE REACTORS
REACTOR INSTRUMENTATION
REACTORS
THERMOCOUPLES
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