Thermal-hydraulic analysis of the dual-function gamma thermometer
A computational study was performed to investigate the potential of a modified gamma thermometer (GT) as a monitor of both the localized power level and the core cooling in a PWR. The volumetric heat source within the thermometer was updated to include heat deposited by neutrons as well as heat deposited by decay gammas and neutron-induced gammas. Utilizing this source, along with a more detailed thermal-hydraulics model, a series of thermal-hydraulic calculations were performed to simulate certain reactor transients of interest (i.e., reactor scram, LOCA, etc.) in order to characterize the gamma thermometer response relative to power level monitoring and adequate core cooling indication. Results of this study reaffirm the feasibility of utilizing the GT as a dual-function (power level and adequate core cooling capacity) measurement device, with each function accomplished virtualy independent of the other. The study also indicates that there is a thermal-hydraulic regime for which the GT would no longer give easily interpretable signals.
- Research Organization:
- Oak Ridge National Lab., TN (USA); Tennessee Univ., Knoxville (USA). Dept. of Nuclear Engineering
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5597995
- Report Number(s):
- ORNL/TM-8089; ON: DE82007344
- Country of Publication:
- United States
- Language:
- English
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46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
ELECTROMAGNETIC RADIATION
FLUID MECHANICS
GAMMA RADIATION
HEATING
HYDRAULICS
IN CORE INSTRUMENTS
IONIZING RADIATIONS
MEASURING INSTRUMENTS
MECHANICS
POWER DENSITY
POWER DISTRIBUTION
PWR TYPE REACTORS
RADIATION HEATING
RADIATIONS
REACTOR INSTRUMENTATION
REACTORS
SIMULATION
THERMOCOUPLES
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS