Published 1980
| Version v1
Miscellaneous
Simulation of a Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant
Description
The following work intends to perform the digital simulation, of the Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant for control systems design and analysis purposes. There are mathematical models for the reactor, the steam generator, the pressurizer and for transport lags of the coolant in the primary circuit. Nevertheless no one control system has been considered to permit any user the inclusion in the more convenient way of the desired control systems' models. The characteristics of the system in consideration are fundamentally equal to the ones of Almirante Alvaro Alberto Nuclear Power Plant, Unit I (Angra I) obtained in the Final Safety Analysis Report at Comissao Nacional de Energia Nuclear. (author)
Availability note (English)
Available from the Library of Comissao Nacional de Energia Nuclear, RJ, Brazil.Additional details
Additional titles
- Original title (Portuguese)
- Simulacao do sistema nuclear de geracao de vapor de uma central PWR
Publishing Information
- Imprint Pagination
- 192 p.
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 23087208
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis, Non-conventional Literature
- Descriptors DEI
- ANGRA-1 REACTOR; MATHEMATICAL MODELS; PWR TYPE REACTORS; SIMULATION; STEAM GENERATION; TRANSIENTS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS