Time response measurements of Angra I nuclear power plant using direct and indirect methodologies
Creators
- 1. Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)
- 2. ELETROBRAS Termonuclear S.A., ELETRONUCLEAR, Angra dos Reis, RJ (Brazil)
Description
Estimation of sensor response characteristics is necessary to satisfy requirements on allowable response time for nuclear power plants. The methodology currently used includes direct and indirect measurements each of them having its vantages and disadvantages. The objective of this work is to compare the time response measurements of temperature and pressure sensors of the Brazilian Angra I nuclear power plant obtained using direct and indirect methodologies. Direct methods give more precise results, but need special equipment do be carried out and interfere with the reactor operation. Indirect methodology is most practical of being performed; it does not interfere with the reactor operation because the sensors do not have to be out of operation. On the other hand, since the parameter identification depends on the noise characteristics, there are cases where indirect methodology is not suitable to predict time response. (author)
Additional details
Publishing Information
- ISBN
- 978-85-99141-02-1
- Imprint Title
- Proceedings of the INAC 2007 International nuclear atlantic conference. Nuclear energy and energetic challenges for 21st. century. 15. Brazilian national meeting on reactor physics and thermal hydraulics; 8. Brazilian national meeting on nuclear applications
- Imprint Pagination
- [vp.]
- Journal Page Range
- [8 p.]
Conference
- Title
- INAC 2007 International nuclear atlantic conference. Nuclear energy and energetic challenges for 21st. century. 15. Brazilian national meeting on reactor physics and thermal hydraulics; 8. Brazilian national meeting on nuclear applications
- Dates
- 30 Sep - 5 Oct 2007
- Place
- Santos, SP (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 39093823
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- ANGRA-1 REACTOR; NUMERICAL DATA; POWER DENSITY; PRESSURE MEASUREMENT; REACTOR INSTRUMENTATION; REACTOR OPERATION; TEMPERATURE MEASUREMENT
- Descriptors DEC
- DATA; ENRICHED URANIUM REACTORS; INFORMATION; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs., 12 figs., 1 tab. Code: R09_776.pdf