Thermal and Mechanical Analysis of a PWR core baffle considering creep


Thermal and Mechanical Analysis of a PWR core baffle considering creep

Altstadt, E.; Fischer, E.; Kumpf, H.; Nagel, G.; Sgarz, G.; Weiss, F.-P.

The core baffle of a PWR is loaded by the pressure difference between bypass and core and by temperature profiles originating from gamma and neutron heating and heat transfer into the coolant. Strain, deformation and gaps between the core baffle sheets resulting from this load are determined considering the effect of neutron irradiation induced creep of the core baffle bolts. The finite element code ANSYS® is applied for the thermal and mechanical analyses. The FE-model comprises a complete 45° sector of the core baffle structure including the core barrel, the formers, the core baffle sheets and about 230 bolt connections with non-linear contact between the single components and the effect of friction. The complete analysis requires three major steps:

· Evaluation of the three dimensional distribution of neutron flux and gamma induced internal heating
· Calculation of the temperature distribution in the core baffle
· Calculation of time dependent deformation, stresses and strains
The results show the equalizing effect of redistribution of bolt loads from high flux to lower flux exposure locations in a self controlled process, keeping the mechanical and geometrical stability of the core baffle structure and leaving the gaps between sheet edges unaffected.

  • ATW - International Journal for Nuclear Power 49(2004)5, 333-336

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