IEA-R1 renewed primary coolant piping system stress analysis
Carregando...
Data
Data de publicação:
2017
Orientador
Título da Revista
ISSN da Revista
Título do Volume
É parte de
É parte de
É parte de
É parte de
60 YEARS OF IEA-R1: INTERNATIONAL WORKSHOP ON UTILIZATION OF RESEARCH REACTORS
Exportar
Resumo
A partial replacement of the IEA-R1 piping system was conducted in 2014. The
aim of this work is to perform the stress analysis of the renewed primary piping system
of the IEA-R1, taking into account the as built conditions and the pipe modifications.
The nuclear research reactor IEA-R1 is a pool type reactor designed by Babcox-
Willcox, which is operated by IPEN since 1957.
The primary coolant system is responsible for removing the residual heat of the
Reactor core. As a part of the life management, a regular inspection detected some
degradation in the primary piping system. In consequence, part of the piping system
was replaced. The partial renewing of the primary piping system did not imply in major
piping layout modifications. However, the stress condition of the piping systems had
to be reanalyzed.
The structural stress analysis of the primary piping systems is now presented and
the final results are discussed.
Como referenciar
FALOPPA, A.A.; FAINER, G.; OLIVEIRA, C.A.; MATTAR NETO, M. IEA-R1 renewed primary coolant piping system stress analysis. In: 60 YEARS OF IEA-R1: INTERNATIONAL WORKSHOP ON UTILIZATION OF RESEARCH REACTORS, November 28 - December 01, 2017, São Paulo, SP. Abstract... São Paulo, SP: Instituto de Pesquisas Energéticas e Nucleares, 2017. p. 86-86. Disponível em: http://repositorio.ipen.br/handle/123456789/28786. Acesso em: 14 May 2024.
Esta referência é gerada automaticamente de acordo com as normas do estilo IPEN/SP (ABNT NBR 6023) e recomenda-se uma verificação final e ajustes caso necessário.