Course title:

Thermal Hydraulics of Nuclear Power Plants

Primary programme:

Fizikus mérnök BSc

ECTS credits:

5

Course type:

elective

Number of lectures per week:

3

Number of practices per week:

1

Number of laboratory exercises per week:

0

Further knowledge transfer methods:

Grading:

Coursework grade

Special grading methods:

midterm-tests

Semester:

5

7

Prerequisites:

Modern Physics, Thermodynamics and Statistical Physics

Responsible lecturer:

Dr. Attila Aszódi, university professor, PhD

Lecturers and instructors:

Course description:

Types and main features of NPPs. Realization of the heat transport technology in different reactor types. The heat production process and its spatial distribution in light-water nuclear reactors. The relationship between the thermal neutron flux distribution and the heat production. Power distribution within the reactor core. Residual heat generation. The general heat conduction differential equation and its solution for the fuel - cladding system. Single-phase hydraulics: the momentum conservation equation for one-dimensional flow; calculations of the friction loss, hydraulic resistance of sudden changes; modelling the velocity distribution and the transport processes in the reactor, mixing, critical flow. Two-phase hydraulics: flow patterns, volume steam content, two-phase flow modelling, pressure drop in two-phase flow, mixing, critical flow. Single-phase heat transfer calculations, natural and forced convection. Two-phase heat transfer calculations. Boiling curve, boiling crisis, critical heat flux, DNBR. Thermal-hydraulics calculation of the pressurized water reactor: conservation equations; temperature distribution in the fuel rod; calculation of the characteristics of the coolant; design limits, hot channel factors. The thermal-hydraulics of design basis accidents. Thermo-physical problems of the re-flooding of the reactor core. Overview of computer programs used in thermal-hydraulics calculations. Subchannel codes and their applications. System codes and their validation. Nuclear safety principles. Design basis. Understanding and applying the thermal-hydraulics system codes for the analysis of incidents. Overview of the most important processes leading to core meltdown in beyond design basis severe accidents and their calculations.

Reading materials:

N.E. Todreas, M.S. Kazimi: Nuclear Systems I; Thermal hydraulic fundamentals, 1990, ISBN 978-1560320517
L.S. Tong, J. Weisman: Thermal Analysis of Pressurized Water Reactors, ANS, 1996, ISBN 978-0-89448-038-6

List of competences:

Please find the detailed list, as quoted from the Hungarian training and outcome requirements of the Physicist Engineer program, in the Hungarian version of the course description.