Development of thermal transit flow measurement for small modular reactors - 140
Creators
- 1. Analysis and Measurement Services -AMS- Corporation 9119 Cross Park Drive, Knoxville, TN 37923 (United States)
Description
Safe, reliable, and efficient operation of nuclear reactors requires timely and accurate measurement of primary coolant parameters such as temperature, flow, pressure, and level. These measurements may be challenging in small modular reactors (SMRs) with integral vessel design. For SMRs with the integral design, sensors may be located in confined spaces or embedded within pressure vessels. The absence of primary coolant loops is another fundamental design attribute that will affect the location of sensors, sensor interfaces, and types of sensors suited for process parameter measurements. Further, the number and location of pressure vessel penetrations may be constrained compared to traditional nuclear power plants (NPPs). As a result, conventional NPP temperature, flow, pressure, and level sensors may not be appropriate for use in SMRs. This paper addresses the development of new sensor technology for hybrid temperature, flow, and level measurement. The authors demonstrate the alternative use of resistance temperature detectors (RTDs) where cross-correlation of process temperature variations between RTDs is used to calculate process flow velocity. The new sensor and measurement technology will also incorporate RTD response time and self-heating characteristics to provide flow and level measurement in accident conditions. This capability would simplify reactor design and enable optimal placement of reactor pressure vessel penetrations leading to increased operational reliability and safety. The cross-correlation of temperature signals and adaptation for flow measurement in a laboratory setting is presented here. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 10 p.
Conference
- Title
- 10. International Conference on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies
- Acronym
- NPIC and HIMIT 2017
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52075653
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEATING; INTEGRALS; NUCLEAR POWER PLANTS; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; REACTOR ACCIDENTS; REACTOR DESIGN; REACTOR OPERATION; REACTOR SAFETY; RELIABILITY; SENSORS; SIGNALS; SMALL MODULAR REACTORS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; COOLING SYSTEMS; DESIGN; ENERGY SYSTEMS; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR LIFE CYCLE; REACTORS; SAFETY; THERMAL POWER PLANTS
Optional Information
- Notes
- 4 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)