Sociedad Española de Integridad Estructural
Grupo Español de Fractura

Sociedad Española de Integridad Estructural
Grupo Español de Fractura

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COMPARISON OF PTS ANALYSES OF RPVS BASED ON 3D-CFD AND RELAP5

V.F. González-Albuixech  G. Qian  M. Sharabi  M. Niffenegger  B. Niceno  N. Lafferty   

Anales de la Mecánica de la Fractura, nº 32 . 2015 . Pág. 298 -303
Ver (.pdf): Anales32-047

Resumen: The integrity of a reactor pressure vessel related to pressurized thermal shocks is one of the most important issues for the assessment of life time extension of a nuclear power plant. One critical scenario occurs during cold water injection through the cold leg due to a Loss-Of-Coolant Accident (LOCA). In the present study, a hypothetical break LOCA is assumed in one of the hot legs for a reference design of a two-loop pressurized water reactor. The boundary conditions obtained from RELAP5 calculations are used as input for the three-dimensional computational fluid dynamics simulations in order to provide three-dimensional temperature distribution for the structural mechanics analysis. The results from these three-dimensional computations and from simplified axisymmetric models based on RELAP5 are compared. Our results show that the simplified axisymmetric models fail to represent the three dimensional effects of the plume, and cannot be regarded as a conservative approach.

LocalizaciónZamora

Laboratory for Nuclear Materials (LNM), Paul Scherrer Institut, Nuclear Energy and Safety Department.
Laboratory for Nuclear Materials (LNM), Paul Scherrer Institut, Nuclear Energy and Safety Department.
Laboratory for Thermo Hydraulics (LTH), Paul Scherrer Institut, Nuclear Energy and Safety Department.
Laboratory for Nuclear Materials (LNM), Paul Scherrer Institut, Nuclear Energy and Safety Department.
Laboratory for Thermo Hydraulics (LTH), Paul Scherrer Institut, Nuclear Energy and Safety Department.
Laboratory for Thermo Hydraulics (LTH), Paul Scherrer Institut, Nuclear Energy and Safety Department.

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