Pressure and flow rate measuring system for Rheinsberg NPP diagnostic fuel rod bundle, operation experience and measurement results
Creators
Description
Pressure and flow rate measuring system for DK 1 type diagnostic fuel rod bundle has been designed, fabricated and put into operation. The system consists of pressure sensors, hydraulic circuit, electronic circuit for signal processing and valve control unit. A detailed description of the hydraulic circuit and the sensor block is given. The valve control unit can be operated both manually and automatically. The automatic operation algorithm is decribed. Types of possible errors and ways to their decrease are discussed. The major difficulties are connected with the errors due to variations in calibration and operation conditions. A method to eliminate these particular errors has been found. As a result the flow rate measurement error was below 5% at the nominal flow rate level and below 10% at the minimal one
Additional details
Additional titles
- Original title (Russian)
- Система измерения давления и расхода диагностической кассеты Райнсбергской АЭС, опыт эксплуатации и результаты измерений
Publishing Information
- Imprint Title
- Thermal physics 82. Thermal aspects of WWER nuclear reactors safety. V. 3.
- Journal Page Range
- p. 147-153.
- Report number
- INIS-mf--9441
Conference
- Title
- Thermal physics 82. Thermal aspects of WWER nuclear reactors safety.
- Dates
- 4-6 May 1982.
- Place
- Karlovy Vary (Czechoslovakia).
INIS
- Country of Publication
- International Centre for Scientific and Technical Information (ICSTI)
- Country of Input or Organization
- International Centre for Scientific and Technical Information (ICSTI)
- INIS RN
- 15072885
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DATA PROCESSING; FLOW RATE; FUEL ASSEMBLIES; IN CORE INSTRUMENTS; MEASURING INSTRUMENTS; PRESSURE MEASUREMENT; REACTOR INSTRUMENTATION; REACTOR OPERATION; RHEINSBERG AKW1 REACTOR
- Descriptors DEC
- ENRICHED URANIUM REACTORS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs.; 4 figs. Imprint:Teplofizika 82. Teplotekhnicheskaya bezopasnost' yadernykh reaktorov WWER. Tom 3.;Sbornik dokladov iz seminara SEhV g. Karlovy Vary, ChSSR, Maj 1982 g.