Sensitivity analysis of fuel rod parameters in steady state condition using TRANSURANUS code
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2019
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INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
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Resumo
In this paper, a simulation of steady state conditions using TRANSURANUS code applied to Arkansas Nuclear
One Unit 2 (PWR) fuel rod is presented. The fuel rod considered in this work was exposed to a peak rod
average burnup of 64 GWd/TU, which corresponds to a batch-average exposure of about 53 GWd/TU.
TRANSURANUS code offers two different approach for sensitivity analysis: Numerical Noise Analysis and
Monte Carlo. In this work, sensitivity analysis using Monte Carlo approach was considered in the range of fuel
rod manufacturing parameters, such as internal and external radius of the cladding, external radius of the fuel,
and filling gas pressure of the fuel rod, in order to verify some existing correlation with fuel centerline
temperature, internal cladding temperature, average tangential stress in the cladding, average permanent
tangential strain in the cladding, internal pressure, and fission gas release.
Como referenciar
AGUIAR, AMANDA A.; ABE, ALFREDO; GIOVEDI, CLAUDIA. Sensitivity analysis of fuel rod parameters in steady state condition using TRANSURANUS code. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 4936-4942. Disponível em: http://repositorio.ipen.br/handle/123456789/30705. Acesso em: 28 Mar 2025.
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.