Kravchenko V. Heat equipment and pipelines of second cycle of the NPP with VVER reliability

Українська версія

Thesis for the degree of Doctor of Science (DSc)

State registration number

0507U000359

Applicant for

Specialization

  • 05.14.14 - Теплові та ядерні енергоустановки

15-05-2007

Specialized Academic Board

Д 41.052.04

Odessa National Polytechnic University

Essay

Founded is the development a comparison method for technical decisions as to nuclear power installations with different parameters of safety. To estimate the safety influence offered is entering the "cost an equivalent of safety” criterion. High pressure heaters (HPH) switching-off influence onto steam generator ПГВ–1000 target collector’s long durability is proved. The reason of asymmetrical arrangement cracks is revealed. Results of HPH hydraulic calculation together with the analysis of coils wall thickness gaugings have been shown, ibidem, the principal cause of erosive corrosion deterioration of entrance sites relates to stream turbulences. Reconstruction of HPH is offered and proved as raising the productivity of electric power. Offered are recommendations which reduce volume of the control of HPH coils. The algorithm of pipelines deterioration forecasting, based on use exhibitor function for a wall thickness time dependent change is resulted. Average speeds of deterioration of technological pipelines are determined.

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