Published 1997
| Version v1
Miscellaneous
Angra-1 operational control systems representation with RELAP5/MOD2 code
Creators
- 1. Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)
Description
The following automatic control systems for Angra-1 NPP were simulated with the RELAP5/MOD2 code: rod control system, steam generator level control system, feedwater bypass valve control system, pressurizer pressure control system and pressurizer level control system. The paper shows the results of two transients: a ten percent step load change and a five percent per minute ramp load change. Satisfactory quantitative and qualitative results were obtained when comparing these results with thermal-hydraulic NPP programmed-values. (author). 7 refs., 13 figs
Additional details
Additional titles
- Original title (Portuguese)
- Representacao dos sistemas de controle operacional de Angra-1 com o codigo RELAP5/MOD2
Publishing Information
- Imprint Title
- Proceedings of the 11. ENFIR: Meeting on reactor physics and thermal hydraulics
- Imprint Pagination
- 838 p.
- Journal Page Range
- p. 490-495.
Conference
- Title
- Meeting on reactor physics and thermal hydraulics.
- Acronym
- 11. ENFIR
- Dates
- 18-22 Aug 1997.
- Place
- Pocos de Caldas, MG (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 28075531
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ANGRA-1 REACTOR; COMPUTER CODES; NUCLEAR ENGINEERING; PWR TYPE REACTORS; R CODES; REACTOR OPERATION; REACTOR PHYSICS; REACTOR TECHNOLOGY; REACTORS; THERMAL ANALYSIS
- Descriptors DEC
- ENGINEERING; ENRICHED URANIUM REACTORS; OPERATION; POWER REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Joint nuclear conference with the 4. ENAN: Brazilian meeting on nuclear applications.