Published July 1982
| Version v1
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Analysis of dynamic behavior of a PWR utilizing the computer program SARDAN 2
Description
In the design of a PWR nuclear plant it is necessary to verify if the design limits are respected, even under abnormal operation condition. An evolution of SARDAN code, developed to simulate transients in PWR, are presented. The new aspects incorporeted in SARDAN 2 are: the fuel ROD analysis in finite-diference, an open channel model for the critic subchannel analysis and the introduction of a simplified model for the automatic control system. The program has been tested in accident condition II, in special, uncontrolled ROD cluster assembly bank withoraw, dropped full-length assembly group, uncontrolled Boron dilution, and the results obtained were considered satisfactory. (Author)
Availability note (English)
MF available from INIS under the Report Number.Abstract (Portuguese)
No projeto de uma usina nuclear PWR, e necessario verificar se os limites de projeto dos seus componentes sao respeitados mesmo em condicoes de operacao anormal. Apresenta-se uma evolucao do programa Sardan, desenvolvido para simulacao de transitorios em PWR' sub(s). Os novos aspectos incorporados na versao Sardan 2, sao: analise da vareta de combustivel ou diferencas finitas, modelo de canal aberto para o subcanal critico e implantacao de um modelo simplificado para o sistema de controle automatico. O programa foi testado em acidentes condicao II, em particular, retirada descontrolada de um conjunto de barras de controle, queda de um conjunto de barras de controle, diluicao descontrolada de boro, e os resultados obtidos considerados satisfatorios. (Autor)Files
14742981.pdf
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Additional details
Additional titles
- Original title (Portuguese)
- Analise do comportamento dinamico de um PWR utilizando o programa SARDAN 2
Publishing Information
- Imprint Pagination
- 276 p.
- Report number
- INIS-mf--7856
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 14742981
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- FUEL RODS; PWR TYPE REACTORS; S CODES; SIMULATION; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; FUEL ELEMENTS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS