Thermal stratification monitoring of Angra 2 steam generator main feedwater nozzles
- 1. Eletrobras Termonuclear S.A. - ELETRONUCLEAR, Rio de Janeiro, RJ (Brazil). Dept. GAN-T
Description
In former times several utilities reported a large temperature excursion in the Steam Generator Main Feedwater nozzles during heat up and cool down of the nuclear plants. In Angra 2 this behavior was also observed and, besides that, thermal stratification during the hot standby mode of operation has also been measured. This behavior was detected thru a temperature monitoring program, in which a set of thermocouples were installed on the external surface of the pipe with the aim to monitor thermal transient. Because the stratification loading has not been defined in the design phase of the system, it is necessary to check the effect of this phenomenon on the fatigue analysis of the piping. This stratification leads to undesired temperature gradients which can conduct to strain and consequently stress in the nozzle material. This behavior can be part of the cause of accelerated fatigue of the component. The objective of this paper is to present the thermal stratification monitoring program implemented in Angra 2 and determined the usage factor of the components due to the phenomenon. (author)
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Additional details
Publishing Information
- Imprint Pagination
- [9 p.]
- Report number
- INIS-BR--6806
Conference
- Title
- International nuclear atlantic conference. Innovations in nuclear technology for a sustainable future; 16. Brazilian national meeting on reactor physics and thermal hydraulics; 9. Brazilian national meeting on nuclear applications; 1. Meeting on nuclear industry
- Acronym
- INAC 2009
- Dates
- 27 Sep - 2 Oct 2009
- Place
- Rio de Janeiro, RJ (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 41072603
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ANGRA-2 REACTOR; DATA ACQUISITION; EXPERIMENTAL DATA; F CODES; FATIGUE; FEEDWATER; NOZZLES; STEAM GENERATORS; TEMPERATURE MONITORING; THERMOCOUPLES
- Descriptors DEC
- BOILERS; COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; INFORMATION; MEASURING INSTRUMENTS; MECHANICAL PROPERTIES; MONITORING; NUMERICAL DATA; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Published only in CD-Rom. Code: i09_597_fullpaper.pdf