Nuclear Fuel and Heat Generating Plants

Major: Nuclear Power Engineering
Code of subject: 6.143.02.E.093
Credits: 5.00
Department: Heat Engineering and Thermal and Nuclear Power Plants
Lecturer: Tetiana Rуmar, Ph.D., Associate Professor
Semester: 5 семестр
Mode of study: денна
Learning outcomes: • the ability to demonstrate knowledge and understanding of nuclear safety issues, in particular, to know the basic types of nuclear fuel and technology of production of fuel materials; • be able to apply knowledge and understanding to identify, formulate and solve technical problems of a specialty, using known methods; • be able to search information from different sources to solve specialty tasks.
Required prior and related subjects: prerequisites • Nuclear and neutron physics; • Nuclear power reactors; co-requisites • Nuclear power plants.
Summary of the subject: Dispersion fuel in nuclear power. Nuclear fuel structure of research reactors. Nuclear fuel dispersion fuel rods of research reactors. High-temperature dispersed nuclear fuel. Use of dispersion fuel for regional energy. High-temperature gas-cooled dispersion fuel. Dispersion fuel for power reactors. Fuel for "burning" plutonium. Types of nuclear fuel dispersion compositions. Nuclear fuel dispersion matrix materials. Graphite as a matrix material of dispersive nuclear fuel. IMF dispersion matrix materials. Matrix materials based on thorium compounds. Nuclear fuel dispersion materials. Uranium and its alloys. Ceramic compounds of nuclear fuel materials. Uranium dioxide. Uranium carbides. Uranium mononitride. Uranium silicides. Plutonium dioxide. Plutonium mononitride.
Assessment methods and criteria: • recitation (30%); • summative assessment (70%, final control-exam): written-oral form
Recommended books: 1. Alekseev S.V., Zaitsev V.A., Tolstoukhov S.S. Nuclear Fuel Dispersion Moscow: TECHNOSPHERE, 2015. - 248 p. 2. Godin Y.G., Tenishev A.V. Carbide Nuclear Fuel: Tutorial. - M .: MIFI, 2007. - 68 p. 3. D.M. Skorov, Yu.F. Bychkov, A.I. Dashkovsky. Reactor material science. - 2nd ed., Remaking. and ext. - M .: Energoatomizdat, 1979. 4. Kotelnikov R.B. etc. High-temperature nuclear fuel. - M .: Atomizdat, 1978. 5. Reshetnikov F.G. et al., Development, production and operation of fuel elements of nuclear reactors. In 2 parts / Ed. F.G. Reshetnikova. - M.: Energoatomizdat, 1995.

Nuclear Fuel and Heat Generating Plants (курсовий проєкт)

Major: Nuclear Power Engineering
Code of subject: 6.143.02.E.094
Credits: 3.00
Department: Heat Engineering and Thermal and Nuclear Power Plants
Lecturer: Tetiana Rуmar, Ph.D., Associate Professor
Semester: 5 семестр
Mode of study: денна
Learning outcomes: • the ability to demonstrate knowledge and understanding of nuclear safety issues, in particular, to know the basic types of nuclear fuel and technology of production of fuel materials; • be able to apply knowledge and understanding to identify, formulate and solve technical problems of a specialty, using known methods; • be able to search information from different sources to solve specialty tasks.
Required prior and related subjects: prerequisites • Nuclear and neutron physics; • Nuclear power reactors; co-requisites • Nuclear power plants.
Summary of the subject: General principles of design of heat-generating elements on the basis of aluminum matrix, stainless steel, magnesium. Performing neutron-physical calculation of nuclear fuel. Calculation of critical and actual core sizes, geometric and material parameters, diffusion length and neutron age, probability of neutron leakage from the core during deceleration and diffusion. Calculation of reactor capacity and mass of nuclear fuel loaded into the reactor.
Assessment methods and criteria: • recitation (30%); • summative assessment (70%, credit): defense of course project.
Recommended books: 1. Alekseev S.V., Zaitsev V.A., Tolstoukhov S.S. Nuclear Fuel Dispersion Moscow: TECHNOSPHERE, 2015. - 248 p. 2. Godin Y.G., Tenishev A.V. Carbide Nuclear Fuel: Tutorial. - M .: MIFI, 2007. - 68 p. 3. D.M. Skorov, Yu.F. Bychkov, A.I. Dashkovsky. Reactor material science. - 2nd ed., Remaking. and ext. - M .: Energoatomizdat, 1979. 4. Kotelnikov R.B. etc. High-temperature nuclear fuel. - M .: Atomizdat, 1978. 5. Reshetnikov F.G. et al., Development, production and operation of fuel elements of nuclear reactors. In 2 parts / Ed. F.G. Reshetnikova. - M.: Energoatomizdat, 1995.