Reconstruction of core inlet temperature distribution by cold leg temperature measurements
Description
The reduced core of Loviisa NPP contains 33 thermocouple measurements measuring the core inlet temperature. Currently, these thermocouple measurements are not used in determining the inlet temperature distribution. The average of cold leg temperature measurements is used as inlet temperature for each fuel assembly. In practice, the inlet temperature distribution is not constant. Thus, using a constant inlet temperature distribution induces asymmetries in the measured core power distribution. Using a more realistic inlet temperature distribution would help us to reduce virtual asymmetries of the core power distribution and increase the thermal margins of the core. The thermocouples at the inlet cannot be used directly to measure the inlet temperature accurately because the calibration of the thermocouples that is done at hot zero power conditions is no longer valid at full power, when there is temperature change across the core region. This is due to the effect of neutron irradiation on the Seebeck coefficient of the thermocouple wires. Therefore, we investigate in this paper a method to determine the inlet temperature distribution based on the cold leg temperature measurements. With this method we rely on the assumption that although the core inlet thermocouple measurements do not measure the absolute temperature accurately they do measure temperature changes with sufficient accuracy particularly in big disturbances. During the yearly testing of steam generator safety valves we observe a large temperature increase up to 12 degrees in the cold leg temperature. The change in the temperature of one of the cold legs causes a local disturbance in the core inlet temperature distribution. Using the temperature changes observed in the inlet thermocouple measurements we are able to fit six core inlet temperature response functions, one for each cold leg. The value of a function at an assembly inlet is determined only by the corresponding cold leg temperature disturbance. The linear combination of the six response functions gives the inlet temperature distribution. In this paper the reconstruction method is described and the effect of inlet temperature distribution on core power distribution is studied. (Authors)
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Additional details
Publishing Information
- Publisher
- Kiadja and KFKI Atomenergia Kutatointezet
- Imprint Place
- Budapest (Hungary)
- ISBN
- 978-963-372-643-3 (OE)
- Imprint Title
- Proceedings of the twentieth symposium of atomic energy research
- Imprint Pagination
- 790 p.
- Journal Page Range
- p. 1-7
- Report number
- INIS-SK--2010-097
Conference
- Title
- 20. Atomic Energy Research Symposium on WWER Physics and Reactor Safety
- Dates
- 20-24 Sep 2010
- Place
- Hanasaari, Espoo (Finland)
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- Slovakia
- INIS RN
- 41131451
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ASYMMETRY; BENCHMARKS; BURNUP; COMPUTER CODES; EXPERIMENTAL DATA; FLOW MODELS; FLOW RATE; FUEL ASSEMBLIES; LOVIISA-1 REACTOR; LOVIISA-2 REACTOR; NUMERICAL DATA; ON-LINE MEASUREMENT SYSTEMS; POWER DISTRIBUTION; PROFITS; RELIEF VALVES; STEAM GENERATORS; TEMPERATURE DISTRIBUTION; TEMPERATURE MEASUREMENT; THERMOCOUPLES; VALIDATION
- Descriptors DEC
- BOILERS; CONTROL EQUIPMENT; DATA; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; INFORMATION; MATHEMATICAL MODELS; MEASURING INSTRUMENTS; NUMERICAL DATA; ON-LINE SYSTEMS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; TESTING; THERMAL REACTORS; VALVES; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 3 figs.; 2 tabs.; 2 refs.