Author, Institution: Gintautas Poškas, Kaunas University of Technology
Science Area, Field of Science: Technological Sciences, Energetics and Power Engineering – 06T
Scientific Supervisor: Prof. Dr. Habil. Gintautas MILIAUSKAS (Kaunas University of Technology, Technological Sciences, Energetics and Power Engineering – 06T).
Scientific Advisor: Prof. Dr. Habil. Vidmantas REMEIKIS (Institute of Physics of Center for Physical Sciences and Technology, Physical Sciences, Physics – 02P).
Dissertation Defence Board of Energetics and Power Engineering Science Field:
Assoc. Prof. Dr. Habil. Algirdas Kaliatka (Lithuanian Energy Institute, Technological Sciences, Energetics and Power Engineering – 06T) – chairman,
Prof. Dr. Habil. Dalis Antanas Baltrūnas (Centre of Physical and Technological Sciences, Physical Sciences, Physics – 02P),
Dr. Viktorija Grigaitienė (Lithuanian Energy Institute, Technological Sciences, Energetics and Power Engineering – 06T),
Prof. Dr. Vladimir Nečas (Slovak University of Technology in Bratislava, Technological Sciences, Energetics and Power Engineering – 06T),
Dr. Raimondas Pabarčius (Lithuanian Energy Institute, Technological Sciences, Energetics and Power Engineering – 06T).
The Doctoral Dissertation is available at the libraries of Kaunas University of Technology (K. Donelaičio St. 20, Kaunas) and Lithuanian Energy Institute (Breslaujos g. 3, Kaunas).
Annotation:
Reliable and cost-effective operational period of nuclear facilities is limited. At the beginning of a decommissioning process, the aim is to dismantle unused equipment with radioactive contamination as efficiently as possible. Naturally, an issue arises of how to determine the radioactive contamination of the nuclear facility’s systems and evaluate its level. The surface contamination level of technological systems is largely influenced by transfer processes and the flows in those systems. Hence, knowledge about these processes and proper evaluation while modelling the contamination of various components of the system are of high importance. The radiological contamination level of systems is a very important criterion when performing a complex evaluation of unused equipment dismantling (cost, radiation dose, work duration, etc.). Such evaluation enables an important principle of the nuclear sustainable development concept at the final stage of the nuclear facility’s lifetime cycle, considering the social, economic, ecological and environmental aspects as well.
The dissertation aims at extending the functionality of numerical modelling software and assessing the radiological contamination of RBMK-1500 nuclear reactor water systems as well as analysing the dismantling process for low contaminated systems.
