Mechanical analysis of a PWR core baffle with consideration of irradiation induced creep of bolts


Mechanical analysis of a PWR core baffle with consideration of irradiation induced creep of bolts

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 developing from gamma heating and heat transfer into the coolant. Strain, deformation and gaps between the sheets resulting from this load are determined con-sidering the effect of neutron irradiation induced creep of the core baffle bolts. The finite ele-ment code ANSYSÒ 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:

1. Evaluation of the three dimensional distribution of neutron flux and gamma induced in-ternal heating with the Monte Carlo code MCNP®. These calculations are based on pin wise power distributions at the core edge for typical loading patterns.
2. Calculation of the temperature distribution in the core baffle for different operational conditions and core loading patterns, considering heat conduction in the components with internal heat sources (gamma heating, step 1) and convectional boundary condi-tions (heat transfer coefficients and bulk temperature of the coolant).
3. Calculation of time dependent deformation, stresses and strains taking into account weight, pressure loads, temperature fields for different load situations (step 2), prestress-ing, irradiation induced creep of the bolts as correlated to neutron flux (step 1).

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.

Keywords: Pressure water reactors; Core baffle; Gamma heating; Monte Carlo transport code; Thermal analysis; Creep; Mechanical stresses; Contact

  • Lecture (Conference)
    2003 International Congress on Advanced Nuclear Power Plants (ICAPP'03), May 4-7, 2003, Cordoba, Spain
  • Contribution to proceedings
    2003 International Congress on Advanced Nuclear Power Plants (ICAPP'03), May 4-7, 2003, Cordoba, Spain

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