Analysis of the combined effects on the fuel performance of UO2-BeO as fuel and iron-based alloy as cladding
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2017
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WATER REACTOR FUEL PERFORMANCE MEETING
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Iron-based alloys have been considered as promising candidate material to replace zirconium-based alloys
as fuel cladding based on the previous experience of the first generation of pressurized water reactors (PWR). Moreover,
the safety margins of nuclear fuels can be improved by means of additives in the fuel pellet, as beryllium oxide (BeO), due
to the increase of the fuel thermal conductivity. These efforts are part of the accident tolerant fuel (ATF) program which
aims to develop nuclear fuel systems with enhanced performance under normal operation, design-basis accident and
severe-accident conditions. This paper addresses the combined effects on the fuel performance considering the BeO
additive in the fuel pellet and stainless steel 348 as cladding material under steady-state and loss-of-coolant-accident
(LOCA) scenario. The fuel performance simulation and assessment are conducted using modified versions of well-known
fuel performance codes (FRAPCON/FRAPTRAN). The obtained results have shown that the studied fuel system (stainless
steel cladding and UO2-BeO) enables an improvement in the main parameters associated to the fuel safety margins under
steady-state irradiation as well as LOCA scenario.
Como referenciar
GIOVEDI, CLAUDIA; ABE, ALFREDO; MUNIZ, RAFAEL O.R.; GOMES, DANIEL S.; SILVA, ANTONIO T. e; MARTINS, MARCELO R. Analysis of the combined effects on the fuel performance of UO2-BeO as fuel and iron-based alloy as cladding. In: WATER REACTOR FUEL PERFORMANCE MEETING, September 10-14, 2017, Jeju Island, Korea. Proceedings... p. 1-9. Disponível em: http://repositorio.ipen.br/handle/123456789/29131. Acesso em: 20 Mar 2026.
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