title: ÐÐ¾Ð´ÐµÐ»Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ Ð¸ Ð¿ÑÐ¾Ð³Ð½Ð¾Ð·Ð¸ÑÐ¾Ð²Ð°Ð½Ð¸Ðµ ÑÑÑÐ°Ð»Ð¾ÑÑÐ½Ð¾Ð³Ð¾ ÑÐ°Ð·ÑÑÑÐµÐ½Ð¸Ñ ÐºÐ¾ÑÐ¿ÑÑÐ° ÑÐµÐ°ÐºÑÐ¾ÑÐ° ÐÐ­Ð¡
title: Ð²ÑÐ¿ÑÑÐºÐ½Ð°Ñ ÐºÐ²Ð°Ð»Ð¸ÑÐ¸ÐºÐ°ÑÐ¸Ð¾Ð½Ð½Ð°Ñ ÑÐ°Ð±Ð¾ÑÐ° ÑÐ¿ÐµÑÐ¸Ð°Ð»Ð¸ÑÑÐ°
titleType: Subtitle
title: Modeling and prediction of fatigue NPP reactor vessel destruction
Creators: name: ÐÐ¸ÐºÑÐ»Ð¸Ð½, ÐÐ»Ð°Ð´Ð¸ÑÐ»Ð°Ð²
Publisher: name: Ð¡Ð°Ð½ÐºÑ-ÐÐµÑÐµÑÐ±ÑÑÐ³ÑÐºÐ¸Ð¹ Ð¿Ð¾Ð»Ð¸ÑÐµÑÐ½Ð¸ÑÐµÑÐºÐ¸Ð¹ ÑÐ½Ð¸Ð²ÐµÑÑÐ¸ÑÐµÑ ÐÐµÑÑÐ° ÐÐµÐ»Ð¸ÐºÐ¾Ð³Ð¾
Year: 2025
Subjects: Ð²Ð²ÑÑ
ÑÑÑÐ°Ð»Ð¾ÑÑÐ½Ð¾Ðµ ÑÐ°Ð·ÑÑÑÐµÐ½Ð¸Ðµ
ÑÐºÐ²Ð¸Ð²Ð°Ð»ÐµÐ½ÑÐ½ÑÐµ Ð½Ð°Ð¿ÑÑÐ¶ÐµÐ½Ð¸Ñ
ÐºÐ¾ÑÐ¿ÑÑ ÑÐµÐ°ÐºÑÐ¾ÑÐ°
ansys
fatigue failure
equivalent stresses
reactor vessel

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description: The diploma thesis is devoted to the analysis of fatigue failure of the WWER-1200 reactor vessel. The main objective of the work is to determine the service life of the vessel under the influence of mechanical and thermal loads, as well as to determine the points that are most vulnerable to fatigue failure. The following tasks were completed during the study: 1. 3D models of reactor vessel elements were created. 2. Ansys 2024 R1 software was validated. 3. Equivalent stresses arising under the influence of coolant pressure in various modes were calculated. 4. Thermal loads caused by temperature changes during operation were analyzed. 5. Combined modeling was performed taking into account thermal cycles and mechanical impact, which allows determining the stress amplitude for subsequent assessment of fatigue failure. The results of the study showed that calculations based only on mechanical loads are unacceptable due to the fact that maximum stresses are achieved in the lower shell nozzles, which contradicts the reactor design, and the obtained service life values are extremely overestimated. Taking into account thermal cycles led to a significant reduction in the estimated service life of the reactor, which is caused by the accelerated accumulation of fatigue damage. It was found that the most dangerous areas of the structure are located in the lateral areas of the hot leg nozzles. The conclusions of the work confirm that the reactor vessel, taking into account all operational loads in the normal mode, is capable of withstanding 700 cycles before fatigue failure. This ensures long-term operation with a limited number of shutdowns, but indicates the imperfection of the calculation, the addition of which can produce a more realistic picture of fatigue failure.