Application of calculation codes for safety analysis of water-water reactors part 2
Course: Nuclear Power Engineering
Structural unit: Faculty of Physics
Title
Application of calculation codes for safety analysis of water-water reactors part 2
Code
ОК13
Module type
Обов’язкова дисципліна для ОП
Educational cycle
Second
Year of study when the component is delivered
2023/2024
Semester/trimester when the component is delivered
2 Semester
Number of ECTS credits allocated
6
Learning outcomes
1.1 Know the algorithms for numerical solution of boundary problems of heat hydraulics of two-phase streams, the structure and features of models of heat hydrohydraulic elements of specialized codes
2.1 Be able to make calculations in specialized codes and analyze their results
Form of study
Full-time form
Prerequisites and co-requisites
- Successful mastering of basic physics courses: "Mechanics", "Molecular Physics", "Electricity", "Optics", "Mathematical Physics", special courses "Fundamentals of Thermohydraulics of Reactor Units"
- Be able to solve problems in basic physics courses.
- Know the composition, purpose and characteristics of the main NPP systems.
- Have basic computer skills to search for information on the Internet
Course content
The purpose of the discipline "Application of calculation codes for safety analysis of PWR reactors Part 2" is to provide students with:
- basic knowledge of computer modeling methods and calculations in the problems of safety analysis of NPPs with PWR reactors
- skills of solving problems of thermohydraulic calculation of equipment and pipelines of nuclear power plants on the basis of heat and mass transfer equations in two-phase flows;
- methods of analysis of calculation results and their use for the purpose of safety analysis of NPP operation
Recommended or required reading and other learning resources/tools
1.Kadenko I.M., Kharitonov O.M., Yermolenko R.V.Fundamentals of heat hydraulics of reactor plants: teaching.manual.- K.: "Kyiv University", 2010.-359рр.
.2. Unified Procedure for Lifetime Assessment of Components and Piping in VVER NPPs “VERLIFE”, Version 5 – Final,EC 5th Euratom Framework Programme 1998-2002.
3. IAEA-EBP-WWER-08 Guidelines on Pressurized Thermal Shock Analysis for WWER Nuclear Power Plants // IAEA, Vienna. - 2006.
4. 20021DL11R-DBA. Database on nuclear steam plant. Zaporizhzhya NPP. Power unit No5., 2002.
5. CATHARE 2 v2.5_2 mod 8.1: Dictionary of Directives and Operators. DEN/DANS/DM2S/STMF/LMES/RT/11-004/A, 2011, 681p.
6. DER/SSTH/LDAS/EM/2005-034 CATHARE2 V2.5_1 : User Guidelines, 2006 – 187p.
Planned learning activities and teaching methods
Lectures; practical training; individual work; consultations.
Assessment methods and criteria
term assessment:
Content module 1
1. Oral answer to the task of individual work or answer questions during the lecture (maximum – 4 points).
2. Performing practical tasks (maximum – 16 points)
3. Modular test (maximum - 10 points)
Content module 2
1. Oral answer to the task of individual work or answer questions during the lecture (maximum – 4 points).
2. Performing practical tasks (maximum – 16 points)
3. Colloquium (maximum - 10 points)
Final assessment in the form of a test
Language of instruction
Ukrainian
Lecturers
This discipline is taught by the following teachers
Departments
The following departments are involved in teaching the above discipline