Vibration monitoring in Angra I nuclear power plant steam generator feedwater system
- 1. Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)
- 2. ELETRONUCLEAR, Rio de Janeiro, RJ (Brazil). Div. de Engenharia
Description
The safety and reliability are the primary criteria in the design and operation of a nuclear power plant. However, due to the aging of the plant and its components, it is difficult to assure that what was originally built and qualified under strict standards is still guaranteed. In order to assure safety, reliability, availability and capacity, aging management through predictive maintenance techniques are being introduced in most plants around the world. In this present work, the monitoring of the vibrations signatures at the Angra I nuclear power plant steam generators feedwater systems main components such as the main feedwater pumps, pressure breaker blocks and the by pass valves, is presented. The vibration data was acquired, afterwards some major repairs were performed and during the startup commissioning procedures. Some of the major repairs performed are: changing of one pump shaft with balancing and alignment, replacement of the original bypass control valves by new disk stack type pneumatic control valves. The results show that no major vibrations anomaly is present after the maintenance indicating adequacy of the repairs made. The monitoring of the vibration in nuclear power plant components is being increasingly used as a tool for predictive maintenance. (author)
Additional details
Additional titles
- Original title (Portuguese)
- Monitoracao de vibracoes nas linhas de recirculacao das bombas de alimentacao do gerador de vapor da usina nuclear ANGRA I
Publishing Information
- Imprint Title
- Proceedings of the INAC 2002: International nuclear atlantic conference; 13. Brazilian national meeting on reactor physics and thermal hydraulics; 6. Brazilian national meeting on nuclear applications
- Imprint Pagination
- [3080 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- International nuclear atlantic conference; 13. Brazilian national meeting on reactor physics and thermal hydraulics; 6. Brazilian national meeting on nuclear applications
- Acronym
- INAC 2002
- Dates
- 11-16 Aug 2002
- Place
- Rio de Janeiro, RJ (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 33046667
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ANGRA-1 REACTOR; AUXILIARY WATER SYSTEMS; DATA ACQUISITION SYSTEMS; EXPERIMENTAL DATA; FEEDWATER; M CODES; REACTOR MAINTENANCE; REACTOR MONITORING SYSTEMS; RELIABILITY; STEAM GENERATORS
- Descriptors DEC
- AUXILIARY SYSTEMS; BOILERS; COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; INFORMATION; MAINTENANCE; NUMERICAL DATA; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs., 3 tabs., 4 graphs Imprint:Published only in CD-Rom