核反应堆物理基础

Nuclear Reactor Physics Basics

Become familiar with nuclear reactor physics and understand what happens in the nuclear reactor core.

1286 次查看
俄罗斯国立核能研究大学
edX
  • 完成时间大约为 6
  • 中级
  • 英语
注:因开课平台的各种因素变化,以上开课日期仅供参考

你将学到什么

Define basic processes that may occur in the reactor core, laws, equations, and the limits of applicability of models describing the neutron field in the reactor;

Demonstrate practical experience of calculating the distribution of neutrons in media;

Demonstrate the ability to analyze the process of slowing down neutrons in various media (typical for nuclear fission reactors) from the standpoint of understanding the physics of the process;

Evaluate important reactor parameters including performance and safety.

课程概况

This engineering course is designed to Introduce students to a range of concepts, ideas and models used in nuclear reactor physics. This course will focus on the physical theory of reactors and methods of experimental studies of the neutron field. This course course is based on the course “Neutron transport theory” which has been taught at the National Research Nuclear University “MEPhI” for the past 20 years.

课程大纲

Section 1. Properties of Free Neutron and Nuclear Fission

Describe the properties of free neutrons and it's classification
Indentify principal nuclear reaction - neutron sources
Define main properties of nuclear fission

Section 2. Interactions of Neutrons with Matter

Define main process of neutron interaction with nuclei of medium
Define microscopic and macroscopic cross sections and mean free path

Section 3. Neutron Field and Main Functions to Describe it

Define neutron flux, net current, one-way currents and vector of net current
Calculate the functions in simple cases

Section 4. Diffusion Theory. Diffusion equation and Fick 's Law

Define main approximations of diffusion theory - Fick's Law and diffusion equation
Explain each term in diffusion equation

Section 5. Solutions of Diffusion Equation in Different Geometries

Define initial and boundary conditions to find solution
Find solutions of diffusion equation in different geometries
Interpret the solutions from physical meaning

Section 6. Solutions of Diffusion Equation in Multiplying Medium

Find and interpret the solution in multiplying medium
Define material and geometry buckling, multiplication factor

Section 7. Main Principals of Slowing down of Neutrons

Define the reason to slow down of neutrons
Explain what nuclear reaction is the best for slowing down
Explain main principals of elastic scattering - post collision energy range, frequency function, mean energy loss per one collision etc.

Section 8. Neutron Spectrum in Non-Absorbing Medium

Define lethargy of neutrons and it's connection to energy
Explain the terms in slowing down equation
Find the solution in non-absorbing medium

Section 9. Neutron Spectrum in Absorbing Medium

Explain the dependency of absorbing cross section to energy
Define Doppler effect, slowing down density, resonance escape probability
Find solution of slowing down equation in absorbing medium

Section 10. Thermalization of Neutrons

Define main principles of neutron behavior in thermal range
Explain ideas to find thermal neutron flux - Maxwell's spectrum
Define averaged cross section, Vescott factors and it's dependency on ambient temperature

Section 11. Multi Group Method

Define energy group
Define principles of getting averaged cross section
Explain the multi group approximation
Find solutions of group diffusion equations

预备知识

Acquisition in math and general physics, basics of integration, first and second order differential equations, vector algebra, math analysis, basics of atomic physics.

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