Research Information System
Thesis Type: Postgraduate
Institution Of The Thesis: Gazi Üniversitesi, Fen Bilimleri Enstitüsü, Turkey
Approval Date: 2019
Thesis Language: Turkish
Student: MEHMET KEMAL ÖZTAŞ
Supervisor: ABUZER ÖZSUNAR
Open Archive Collection: AVESIS Open Access Collection
Abstract:The need for energy is increasing day by day in industrialized countries. One of the different types of power plants to meet energy demands is nuclear power plants that require high technology. The heart of nuclear power plants can be defined as reactor pressure vessels. Reactor pressure vessels are exposed to many corrosive factors such as temperature, pressure, radiation, chemical corrosion etc. during their operating lifetime. Taking these issues into consideration during the design phase, producing a safe reactor pressure vessel is of great importance both for operational safety, human health and nature. The reactor pressure vessels used in nuclear power plants operation under high temperature and pressure. Different countries can use different materials for reactor pressure vessels around the world. In this thesis, finite element analysis was performed for two different material groups under different temperature, pressure and bolt prestress load for a designed reactor pressure vessel. Modeling was performed with ANSYS Spaceclaim and structural analysis was performed with ANSYS Workbench. The behavior of different materials under different loads was examined under ASME and PNAE G-7 codes. While the permissible stress limits for the upper cap, body and nut were not exceeded in both material groups, it was determined that the limits were exceeded for the bolt under different temperature, pressure and bolt pretension load for both materials. The results obtained by finite element analysis showed the performance of the components of the reactor pressure vessel for two different material groups.