On the issue of investigating the strength of the IVV.10M reactor vessel and internals

The questions of strength and seismic stability of a new water-moderated water-cooled research reactor are examined. A computational method is developed and numerical investigation of static capacity and stability, brittle fracture resistance, long-term static capacity, long-term cyclic strength, and seismic load response is carried out. The most loaded parts in the reactor vessel and internals are identified, and quantitative estimates of the deflected mode parameters in risk areas are obtained. The results of calculations are compared with normative documents applicable in the domestic nuclear power industry. The equivalence of new design solutions to the requirements of reactor plant trouble-free operation during the life cycle not only under normal operating conditions but also in an extreme situation, in particular, by an earthquake, is proved.