Design and testing of a thermal liquid level sensor
Creators
Description
During a reactor accident involving loss of coolant inventory, it is important to know the liquid level inside the reactor. Several techniques are available to accomplish this type of measurement, including pressure sensors, floats, and acoustic devices. Another technique involves the use of a directly or indirectly heated thermocouple to determine changes in the heat transfer coefficient on the outer surface of a level probe, such as would occur when a drop in liquid level exposes the probe to a gaseous environment. This paper presents the design and data from the testing of a thermal liquid level sensor, using an indirectly heated thermocouple. The probe has been specifically designed for use in the heavy-water-cooled and -moderated reactors at the Savannah River Plant (SRP)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 59
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 205-206
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Annual meeting of the American Nuclear Society.
- Dates
- 4-8 Jun 1989.
- Place
- Atlanta, GA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21076325
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEAT TRANSFER; HYDRAULICS; LEVEL INDICATORS; LOSS OF COOLANT; PERFORMANCE; PRIMARY COOLANT CIRCUITS; PROBES; PRODUCTION REACTORS; REACTOR ACCIDENTS; REACTOR INSTRUMENTATION; REACTOR MONITORING SYSTEMS; REACTOR SAFETY; SAVANNAH RIVER PLANT; THERMOCOUPLES
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY TRANSFER; MEASURING INSTRUMENTS; NATIONAL ORGANIZATIONS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; US AEC; US DOE; US ERDA; US ORGANIZATIONS
Optional Information
- Secondary number(s)
- CONF-890604--.