Method for temperature measurement confidence control in the process of WWER reactor operation
Creators
Description
Method for computation of the temperature measurement confidence limit of WWER reactor coolant at reactor inlet and outlet and fuel assembly inlet is suggested. The temperature calculated value at reactor outlet is determined as a function of saturation pressure in steam generators. Computation data are compared to the service data for WWER-440 reactor. The suggested method makes it possible to automize the data processing and to increase accuracy of measured and calculated values determination. Increase of the temperature control accuracy and reliability permits to use nuclear reactor and NPP reserve power. Automatic data processing permits to determine energy release fields in a nuclear reactor that increases the accuracy of determining nuclear fuel burn-up, time of fuel cycle
Additional details
Additional titles
- Original title (Russian)
- Метод контроля достоверности температурных измерений при работе реактора ВВЭР
Publishing Information
- Journal Title
- Ehlektr. Stn.
- Journal Issue
- no.10
- Series
- Ehlektr. Stn.
- ISSN
- 0013-5372
- CODEN
- EKSTA
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- USSR
- INIS RN
- 18065890
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCURACY; KOLA-1 REACTOR; LIMITING VALUES; REACTOR COOLING SYSTEMS; TEMPERATURE MONITORING
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; MONITORING; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- For English translation see the journal Soviet Power Engineering (English Translation).