link Источник: www.edx.org
list 6 последовательности
assignment Уровень : Средний
chat_bubble_outline Язык : английский
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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.

  • 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.

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Специальные требования

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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Программа

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
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Пользователи

Yury N. Volkov
Senior lecturer, PhD in Nuclear Engineering
National Research Nuclear University “MEPhI”

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Разработчик

National Research Nuclear University MEPhI
National Research Nuclear University “MEPhI” is one of the most recognized technical universities in Russia. It is the only research nuclear university in Russia. The aim of the university existence is preparing the specialists for nuclear industry, science, information technology and other high-tech sectors of Russian economy. National Research Nuclear University “MEPhI” implements postgraduate professional education curricula (PhD and postdoctoral level), carries out fundamental and applied scientific research in high-priority fields of science and technologies. Among MEPhI graduates are Nobel Prize winners, members of the Russian Academy of Sciences, and winners of national prizes. Its professors and alumni have made major contributions to various fields of theoretical and experimental physics, mathematics, cybernetics, and computer sciences.
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Платформа

Edx

EdX est une plateforme d'apprentissage en ligne (dite FLOT ou MOOC). Elle héberge et met gratuitement à disposition des cours en ligne de niveau universitaire à travers le monde entier. Elle mène également des recherches sur l'apprentissage en ligne et la façon dont les utilisateurs utilisent celle-ci. Elle est à but non lucratif et la plateforme utilise un logiciel open source.

EdX a été fondée par le Massachusetts Institute of Technology et par l'université Harvard en mai 2012. En 2014, environ 50 écoles, associations et organisations internationales offrent ou projettent d'offrir des cours sur EdX. En juillet 2014, elle avait plus de 2,5 millions d'utilisateurs suivant plus de 200 cours en ligne.

Les deux universités américaines qui financent la plateforme ont investi 60 millions USD dans son développement. La plateforme France Université Numérique utilise la technologie openedX, supportée par Google.

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