Published 1989
| Version v1
Miscellaneous
Simplified model for transient analysis in liquid metal cooled reactors
Description
In this paper some details of a simplified model for transient analysis of pool type liquid metal fast reactors are presented. This model, which calculates the transient mass flow rate and sodium temperatures, can be used for adequate components set up within reactor vessel, that obey structural requirements. The details presented are the intermediary heat exchanger and the pump models, and a mathematical method for the solution of coupled differential equations. These models and method were verified by illustractive calculations of two transients in a typical fast reactor with hot pool, which were compared with the results of other researchers. (author)
Availability note (English)
Available from the Library of Comissao Nacional de Energia Nuclear, RJ, Brazil.Abstract (Portuguese)
Neste trabalho sao apresentados alguns detalhes de um modelo simplificado para analise de transientes em reatores rapidos de metal liquido tipo piscina. Esse modelo calcula a vazao transiente e as temperaturas do sodio, podendo ser utilizado para o adequado arranjo dos diversos componentes dentro do vaso, que satisfacam requisitos estruturais. Os detalhes apresentados sao o modelo do trocador de calor intermediario, o modelo da bomba e um metodo matematico de solucao das equacoes diferenciais acopladas. Esses modelos e metodos foram verificados atraves de calculos ilustrativos de dois transientes em um reator rapido tipico com piscina quente, que foram comparados com resultados de outros pesquisadores. (autor)Additional details
Additional titles
- Original title (Portuguese)
- Modelo simplificado para analise de transitorios em reatores refrigerados com sodio liquido
Publishing Information
- Imprint Title
- Proceedings of the 7. National Meeting of Reactor Physics and Thermohydraulic. v. 2
- Imprint Pagination
- 416 p.
- Journal Page Range
- p. 231-241.
Conference
- Title
- 7. National Meeting of Reactor Physics and Thermohydraulic.
- Dates
- 26-28 Apr 1989.
- Place
- Recife, PE (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 20061251
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DIFFERENTIAL EQUATIONS; FLOW RATE; LIQUID METAL COOLED REACTORS; MATHEMATICAL MODELS; TEMPERATURE MEASUREMENT; TRANSIENTS
- Descriptors DEC
- EQUATIONS; REACTORS
Optional Information
- Notes
- Imprint:Anais do 7. Encontro Nacional de Fisica de Reatores e Termohidraulica. v. 2.