Título: | ANALYSIS OF DYNAMIC BEHAVIOR OF A PWR UTILIZING THE COMPUTER PROGRAM SARDAN 2 | ||||||||||||
Autor: |
JORGE ALEXANDRE ONODA PESSANHA |
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Colaborador(es): |
PEDRO CARAJILESCOV - Orientador |
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Catalogação: | 09/ABR/2018 | Língua(s): | PORTUGUESE - BRAZIL |
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Tipo: | TEXT | Subtipo: | THESIS | ||||||||||
Notas: |
[pt] Todos os dados constantes dos documentos são de inteira responsabilidade de seus autores. Os dados utilizados nas descrições dos documentos estão em conformidade com os sistemas da administração da PUC-Rio. [en] All data contained in the documents are the sole responsibility of the authors. The data used in the descriptions of the documents are in conformity with the systems of the administration of PUC-Rio. |
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Referência(s): |
[pt] https://www.maxwell.vrac.puc-rio.br/projetosEspeciais/ETDs/consultas/conteudo.php?strSecao=resultado&nrSeq=33542&idi=1 [en] https://www.maxwell.vrac.puc-rio.br/projetosEspeciais/ETDs/consultas/conteudo.php?strSecao=resultado&nrSeq=33542&idi=2 |
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DOI: | https://doi.org/10.17771/PUCRio.acad.33542 | ||||||||||||
Resumo: | |||||||||||||
In the design of a PWR nuclear plant it is necessary to verify if the design limits are respected, even under abnormal operation condition. The present work represents an evolution of SARDAN code, developed to simulate transients in PWR, 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.
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