Monitoring reactor vessel liquid level with a vertical string of self-powered neutron detectors

Journal Article · Thu Nov 01 00:00:00 EST 1984 · Nucl. Sci. Eng.; (United States)

OSTI ID:6219347

Adams, J P; Berta, V T

Changes in in-core self-powered neutron detector signals, recorded during a nuclear loss of coolant accident (LOCA) simulation, have been correlated with liquid level changes that occurred during the core uncovery and recovery events. The correlations indicate that these detectors can be used to monitor reactor vessel liquid level during a LOCA. A display and alarm system using these detectors to provide reactor operators with an indication of a core uncovery and subsequent thermal excursion and with a means to measure the effectiveness of LOCA recovery procedures is described.

• Research Organization: EG and G Idaho, Inc. Idaho Falls, Idaho
• OSTI ID: 6219347
• Journal Information: Nucl. Sci. Eng.; (United States), Vol. 88:3
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
LOSS OF COOLANT
NEUTRON DETECTORS
REACTOR VESSELS
ALARM SYSTEMS
DISPLAY DEVICES
FLOW RATE
IN CORE INSTRUMENTS
MONITORING
REACTOR CORE DISRUPTION
REACTOR OPERATORS
REACTOR PROTECTION SYSTEMS
SIGNALS
SIMULATION
ACCIDENTS
CONTAINERS
MEASURING INSTRUMENTS
PERSONNEL
RADIATION DETECTORS
REACTOR ACCIDENTS
REACTOR INSTRUMENTATION
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories