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.
Nuclear Reactor Physics Basics
제공자:
Nuclear Reactor Physics Basics
모스크바공학물리연구소 부속 국립원자력대학
About this Course
최근 조회 13,333회
100% 온라인
지금 바로 시작해 나만의 일정에 따라 학습을 진행하세요.
유동적 마감일
일정에 따라 마감일을 재설정합니다.
중급 단계
완료하는 데 약 17시간 필요
권장: 9 hours/week
영어
자막: 영어
강의 계획 - 이 강좌에서 배울 내용
완료하는 데 5시간 필요
Introductions to Nuclear Reactor Physics
In this module students will learn about the neutron field and main functions to describe it. Students will study the concepts of neutron flux, net current, one-way currents and vector of net current.
완료하는 데 5시간 필요
10개 동영상 (총 51분), 10 readings, 6 quizzes
10개의 동영상
The Properties of Free Neutrons and It’s Classification8m
Principal Nuclear Reaction – Neutron Sources4m
Main Properties of Nuclear Fission6m
Main Process of Neutron Interaction With Nuclei of Medium4m
Microscopic Cross-Sections6m
Mean Free Path2m
Neutron Flux, Net Current, One-Way Currents and Vector of Net Current7m
Neutron flux, net current, one-way currents and vector of net current. Example 11m
Neutron Flux, Net Current, One-Way Currents and Vector of Net Current. Example 243
10개의 읽기 자료
Introduction10m
The Properties of Free Neutrons and It’s Classification10m
Principal Nuclear Reaction – Neutron Sources10m
Main Properties of Nuclear Fission10m
Main Process of Neutron Interaction With Nuclei of Medium10m
Microscopic Cross-Sections10m
Mean Free Path10m
Neutron Flux, Net Current, One-Way Currents and Vector of Net Current10m
Neutron Flux, Net Current, One-Way Currents and Vector of Net Current. Example 110m
Neutron Flux, Net Current, One-Way Currents and Vector of Net Current. Example 210m
6개 연습문제
Training test21m
Quiz42m
Training test21m
Quiz27m
Training test21m
Quiz30m
완료하는 데 4시간 필요
Neutrons space behaviour by diffusion aproximation
In this module students will get knowledge concerning neutrons space behavior by diffusion approximation. Students will learn about diffusion theory, diffusion equation and Fick’s Law.
완료하는 데 4시간 필요
9개 동영상 (총 35분), 9 readings, 6 quizzes
9개의 동영상
Fick’s Law4m
Diffusion Equation3m
Initial and Boundary Conditions to Find Solution7m
Task 1. Point Source in Infinite Spherical Geometry3m
Task 2. Plane Source in Infinite Planar Geometry1m
Task 3. Thread-Like Source in Infinite Cylindrical Geometry57
Task 4. Distributed Source in Bare Slab2m
The Solution in Multiplying Medium5m
9개의 읽기 자료
Diffusion Theory10m
Fick’s Law10m
Diffusion Equation10m
Initial and Boundary Conditions to Find Solution10m
Task 110m
Task 210m
Task 310m
Task 410m
The Solution in Multiplying Medium10m
6개 연습문제
Training test21m
Quiz30m
Training test21m
Quiz30m
Training test9m
Quiz30m
완료하는 데 2시간 필요
Main Principals of Slowing down of Neutrons
In this module students will get knowledge concerning Main Principals of Slowing down of Neutrons. Students will learn about Neutron Spectrum in Absorbing and Non-Absorbing Medium.
완료하는 데 2시간 필요
3개 동영상 (총 19분), 3 readings, 2 quizzes
3개의 동영상
Kinematic of Slowing Down8m
Average Logarithmic Energy Loss3m
3개의 읽기 자료
Main Principals of Slowing down of Neutrons10m
Kinematic of Slowing Down10m
Average Logarithmic Energy Loss10m
2개 연습문제
Training test15m
Quiz30m
완료하는 데 3시간 필요
Neutron Spectrum in Non-Absorbing and Absorbing Medium
In this module we will find the dependency of neutron flux by energy (the neutron spectrum). After studding this module, the student should be able to understand and explain the terms in slowing down equation.
완료하는 데 3시간 필요
5개 동영상 (총 29분), 5 readings, 4 quizzes
5개의 동영상
Slowing Down with Absorption4m
Weak Absorption and Resonance Range6m
Resonance Escape Probability3m
Doppler Effect3m
5개의 읽기 자료
Neutron Spectrum in Non-Absorbing Medium10m
Slowing Down with Absorption10m
Weak Absorption and Resonance Range10m
Resonance Escape Probability10m
Doppler Effect10m
4개 연습문제
Training test12m
Quiz27m
Training test15m
Quiz30m
완료하는 데 2시간 필요
Thermalization of Neutrons and MultiGroup Method
In this module students will learn about main principles of neutron behavior in thermal range. Students will study the ideas of find thermal neutron flux — Maxwell’s spectrum.
완료하는 데 2시간 필요
3개 동영상 (총 19분), 3 readings, 4 quizzes
3개의 읽기 자료
Thermalization of Neutrons10m
Multigroup Method10m
Multigroup Method. Examples10m
4개 연습문제
Training test18m
Quiz30m
Training test9m
Quiz30m
모스크바공학물리연구소 부속 국립원자력대학 정보
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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