Analysis of proposed gamma-ray detection system for the monitoring of core water inventory in a pressurized water reactor
An initial study has been performed of the feasibility of employing an axial array of gamma detectors located outside the pressure vessel to monitor the coolant in a PWR. A one-dimensional transport analysis model is developed for the LOFT research reactor and for a mock-PWR geometry. The gamma detector response to coolant voiding in the core and downcomer has been determined for both geometries. The effects of various conditions (for example, time after shutdown, materials in the transport path, and the relative void fraction in different water regions) on the detector response are studied. The calculational results have been validated by a favorable comparison with LOFT experimental data. Within the limitations and approximations considered in the analysis, the results indicate that the gamma-ray detection scheme is able to unambiguously respond to changes in the coolant inventory within any vessel water region.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5430041
- Report Number(s):
- ANL-87-29; ON: DE88005785
- Country of Publication:
- United States
- Language:
- English
Similar Records
Ex-vessel water-level and fission-product monitoring for LWR
Ex-core water-level monitor: comparison of computations with LOFT data
Determination of the coolant and core status during the TMI-2 accident from the ex-core detector responses
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:7164503
Ex-core water-level monitor: comparison of computations with LOFT data
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6993036
Determination of the coolant and core status during the TMI-2 accident from the ex-core detector responses
Thesis/Dissertation
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:6978913
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATTENUATION
COMPUTERIZED SIMULATION
COOLING SYSTEMS
DATA
DETECTION
ENERGY SYSTEMS
EXPERIMENTAL DATA
GAMMA DETECTION
INFORMATION
LOFT REACTOR
LOSS OF COOLANT
NEUTRON FLUX
NUMERICAL DATA
PRESSURIZERS
PWR TYPE REACTORS
RADIATION DETECTION
RADIATION FLUX
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR MONITORING SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
SOURCE TERMS
TANK TYPE REACTORS
TEST REACTORS
THEORETICAL DATA
VOID FRACTION
VOIDS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATTENUATION
COMPUTERIZED SIMULATION
COOLING SYSTEMS
DATA
DETECTION
ENERGY SYSTEMS
EXPERIMENTAL DATA
GAMMA DETECTION
INFORMATION
LOFT REACTOR
LOSS OF COOLANT
NEUTRON FLUX
NUMERICAL DATA
PRESSURIZERS
PWR TYPE REACTORS
RADIATION DETECTION
RADIATION FLUX
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR MONITORING SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
SOURCE TERMS
TANK TYPE REACTORS
TEST REACTORS
THEORETICAL DATA
VOID FRACTION
VOIDS
WATER COOLED REACTORS
WATER MODERATED REACTORS