A Procedure to Address the Fuel Rod Failures during LB-LOCA Transient in Atucha-2 NPP | Zendy

Martina Adorni | Zendy; Alessandro Del Nevo | Zendy; Francesco Saverio D'Auria | Zendy; O. Mazzantini | Zendy

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A Procedure to Address the Fuel Rod Failures during LB-LOCA Transient in Atucha-2 NPP

Author(s) -

Martina Adorni,

Alessandro Del Nevo,

Francesco Saverio D'Auria,

O. Mazzantini

Publication year - 2011

Publication title -

science and technology of nuclear installations

Language(s) - English

Resource type - Journals

SCImago Journal Rank - 0.417

H-Index - 24

eISSN - 1687-6083

pISSN - 1687-6075

DOI - 10.1155/2011/929358

Subject(s) - transient (computer programming) , thermal hydraulics , nuclear engineering , cladding (metalworking) , engineering , source code , thermal , computer science , mechanical engineering , simulation , materials science , mechanics , heat transfer , physics , metallurgy , operating system , meteorology

Depending on the specific event scenario and on the purpose of the analysis, the availability of calculation methods that are not implemented in the standard system thermal hydraulic codes might be required. This may imply the use of a dedicated fuel rod thermomechanical computer code. This paper provides an outline of the methodology for the analysis of the 2A LB-LOCA accident in Atucha-2 NPP and describes the procedure adopted for the use of the fuel rod thermomechanical code. The methodology implies the application of best estimate thermalhydraulics, neutron physics, and fuel pin performance computer codes, with the objective to verify the compliance with the specific acceptance criteria. The fuel pin performance code is applied with the main objective to evaluate the extent of cladding failures during the transient. The procedure consists of a deterministic calculation by the fuel performance code of each individual fuel rod during its lifetime and in the subsequent LB-LOCA transient calculations. The boundary and initial conditions are provided by core physics and three-dimensional neutron kinetic coupled thermal-hydraulic system codes calculations. The procedure is completed by the sensitivity calculations and the application of the probabilistic method, which are outside the scope of the current paper

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