Theory of Nuclear Reactors, part 2

Major: Nuclear Power Engineering
Code of subject: 6.143.00.O.034
Credits: 3.00
Department: Heat Engineering and Thermal and Nuclear Power Plants
Lecturer: Dr. Science Professor. Lukiyanets Bohdan
Semester: 6 семестр
Mode of study: денна
Learning outcomes: On the basis of the studied course "Theory of nuclear reactors, part 1", student will get knowledge about classification of lattices, nonstationary processes in reactors, physical properties and calculations of energy characteristics of different types of reactors - water-moderated water-cooled, graphite, fast breeder reactors. Such knowledge will be useful for future professional practice.
Required prior and related subjects: Higher Mathematics Physics Nuclear Power Units
Summary of the subject: Theory of critical dimensions. Lattice еheory. Non-stationary processes in reactors. Physical and structural peculiarities of different types of reactors - water-moderated water-cooled, graphite, fast breeder reactors. Calculations of energy characteristics of reactors
Assessment methods and criteria: oral examination during the workshops, evaluation of home practical tasks, control work (30%);final control (70%, exam), written-oral form (70%)
Порядок та критерії виставляння балів та оцінок: 100-88 points - certified with an “excellent” grade - High level: the student demonstrates an in-depth mastery of the conceptual and categorical apparatus of the discipline, systematic knowledge, skills and abilities of their practical application. The mastered knowledge, skills and abilities provide the ability to independently formulate goals and organize learning activities, search and find solutions in non-standard, atypical educational and professional situations. The applicant demonstrates the ability to make generalizations based on critical analysis of factual material, ideas, theories and concepts, to formulate conclusions based on them. His/her activity is based on interest and motivation for self-development, continuous professional development, independent research activities, implemented with the support and guidance of the teacher. 87-71 points - certified with a grade of “good” - Sufficient level: involves mastery of the conceptual and categorical apparatus of the discipline at an advanced level, conscious use of knowledge, skills and abilities to reveal the essence of the issue. Possession of a partially structured set of knowledge provides the ability to apply it in familiar educational and professional situations. Aware of the specifics of tasks and learning situations, the student demonstrates the ability to search for and choose their solution according to the given sample, to argue for the use of a particular method of solving the problem. Their activities are based on interest and motivation for self-development and continuous professional development. 70-50 points - certified with a grade of “satisfactory” - Satisfactory level: outlines the mastery of the conceptual and categorical apparatus of the discipline at the average level, partial awareness of educational and professional tasks, problems and situations, knowledge of ways to solve typical problems and tasks. The applicant demonstrates an average level of skills and abilities to apply knowledge in practice, and solving problems requires assistance, support from a model. The basis of learning activities is situational and heuristic, dominated by motives of duty, unconscious use of opportunities for self-development. 49-00 points - certified with a grade of “unsatisfactory” - Unsatisfactory level: indicates an elementary mastery of the conceptual and categorical apparatus of the discipline, a general understanding of the content of the educational material, partial use of knowledge, skills and abilities. The basis of learning activities is situational and pragmatic interest.
Recommended books: 1.Bases of theory and calculation methods of nuclear power reactor (ed.H.A.Bat’). - M .: Energoizdat, 1982. - 507 p. (in Russian) 2. S. Shirokov nuclear power reactors. K. 1997, p. 280. (in Russian) 3. Merzlykyn GY Basis of theory of nuclear reactors. - Sevastopol, 2001 (in Russian)