Analysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulation
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2019
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INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE
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During operation of a Pressurized Water Reactor, the cladding of the fuel rod is subjected to
various loads, such as: temperature, internal pressure, and external pressure which generate
dimensional and geometric variations in the cladding tube. In the fuel rod, at the operating
temperature, the internal pressure comes from the initial pre-pressurizing with Helium gas
and the release of fission gases by the UO2 pellets during the irradiation. The external
pressure is assumed to be the same as that of the coolant. In this paper, it was proposed the
study of a mathematical model for computational simulation using the Finite Element
Method to calculate and analyze the mechanical stresses acting on the internal and external
surfaces of the fuel rod, adopting the normal operating condition, at 0 W of power. The
boundary conditions, such as temperature and pressure profile, come from a modified version
of a fuel performance code, considering as cladding material an iron-based alloy (austenitic
stainless steel). The fuel rod was modeled and simulated using the Solidworks and ANSYS
softwares, respectively. The values of the stresses acting on the cladding tube obtained by
simulation were compared to the values obtained by analytical calculation. Then, it was
checked the consistency of the adopted mathematical model, in order to ensure the reliability
of the computational simulation as a tool to evaluate the stresses acting on the internal and
external surfaces of the fuel rod under a PWR environment.
Como referenciar
LIMA, LEONARDO S.; MELO, CAIO; FARIA, DANILO P.; BERRETA, JOSE; ABATI, AMANDA; GIOVEDI, CLAUDIA. Analysis of stresses acting on the internal and external surfaces of fuel rod of a pressurized water reactor using computational simulation. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, October 21-25, 2019, Santos, SP. Proceedings... Rio de Janeiro: Associação Brasileira de Energia Nuclear, 2019. p. 4950-4961. Disponível em: http://repositorio.ipen.br/handle/123456789/30813. Acesso em: 29 Mar 2025.
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