 
Abstract/Syllabus:

Yip, Sidney, 22.106 Neutron Interactions and Applications, Spring 2005. (Massachusetts Institute of Technology: MIT OpenCourseWare), http://ocw.mit.edu (Accessed 07 Jul, 2010). License: Creative Commons BYNCSA
Neutron Interactions and Applications
Spring 2005
Instead of projecting ions against a single screen, this version of Lawrence Berkeley National Laboratory's compact neutron generator produces many more neutrons by wrapping the target around the ion source. Such neutron generators are small enough to descend into a borehole, provide neutrons for braincancer therapy, and peer inside airport luggage. (Illustration courtesy of the U.S. Department of Energy's Office of Science.)
Course Highlights
This course features problem sets, a sample project, and a complete set of fulltext lecture notes.
Previous versions of this course are also available: Spring 2004, Spring 2002.
Course Description
This course is a foundational study of the effects of single and multiple interactions on neutron distributions and their applications to problems across the Nuclear Engineering department  fission, fusion, and RST. Particle simulation methods are introduced to deal with complex processes that cannot be studied only experimentally or by numerical solutions of equations. Treatment will emphasize basic concepts and understanding, as well as showing the underlying scientific connections with current research areas.
Syllabus
Overview
This subject deals with neutron interactions, particularly elastic and inelastic (in the molecular sense) scattering, and the various applications made possible by these processes, from fission reactor criticality to radiation damage, microdosimetry, imaging, and fundamental research. A particular distinction in the treatment is made between effects of single collisions and the distributions resulting from multiple collisions. Another feature of the subject is the introduction of particle simulation techniques, both Monte Carlo and molecular dynamics, as practical approaches to determining the various distributions. The intent is to provide the student with a unified framework for the quantitative understanding of the complex behavior of nuclear systems.
The course is motivated by the combination of two themes, the study of particle distributions as a consequence of many nuclear interactions, and the widespread use of simulation to determine particle distribution in complex Nuclear Engineering problems. Within ten years the way we think of neutrons will change due to a roughly 8 orders of magnitude increase in computational power, brought on by faster chip speeds, automated variance reduction and parallel processing (Beowulf clusters). To be ready, today's students must master, in the broadest sense, the fundamentals of theory and computation. 22.106 will get you started on that path.
Format
Subject will be taught on the basis of class lectures with supplemental materials distributed or assigned in class. There will be several problem sets, a term project, a written quiz, and an oral exam at the end of the term.
Prerequisite
Applied Nuclear Physics (22.101)
Grading
Course grading.
activities 
percentages 
Problem Sets 
30% 
Term Project 
20% 
Quiz 
30% 
Oral Exam 
20% 
Calendar
Course calendar.
Lec # 
topics 
key dates 
1 
Overview: Neutron Interactions and Cross Sections 

24 
Neutron Elastic Scattering: Thermal Motion and Chemical Binding Effects 
Problem set 1 due in lecture 4 
5 
Particle Simulations I: Monte Carlo Basics 

67 
Further Discussions: Monte Carlo in Statistical Physics and Radiation Transport 
Problem set 2 due in lecture 7 
8 
The Neutron Transport Equation: A Balance of Distributions 

9 
Neutron Slowing Down 
Problem set 3 due 
10 
Neutron Diffusion 

11 
Criticality of Multiplying Systems 

12 
Particle Simulation Methods II: Basic Molecular Dynamics 
Problem set 4 due seven days after lecture 12
Problem set 5 due fourteen days after lecture 12 
13 
An Application of Molecular Dynamics: Direct Simulation of Melting 

14 
Multiscale Materials Modeling 
Problem set 6 due 
15 
Thermal Neutron Scattering Basics 

16 
Dynamic Structure Factor in Neutron Inelastic Scattering 
Problem set 7 due five days after lecture 16
Quiz due 7 days after lecture 16 



Further Reading:

Readings
The course is taught on the basis of class lectures with supplemental materials distributed or assigned in class. Below is a list of other useful reference materials. Lecturespecific references are found within the lecture notes files.
General References
Byrne, J. Neutrons, Nuclei and Matter: An Exploration of the Physics of Slow Neutrons. New York: Taylor & Francis Inc., 1996. ISBN: 9780750303668.
Parks, D. E., M. S. Nelkin, J. R. Beyster, and N. F. Wikner. Slow Neutron Scattering and Thermalization. New York, NY, W. A. Benjamin, 1970.
Foderaro, A. The Elements of Neutron Interaction Theory. Cambridge, MA: MIT Press, 1971. ISBN: 9780262561600.
Marshall, W., and S. W. Lovesey. Theory of Thermal Neutron Scattering. Oxford, UK: Clarendon Press, 1971.
Lamarsh, J. R. Introduction to Nuclear Reactor Theory. Reading, MA: AddisonWesley, 1966.
Duderstadt, J. J., and W. R. Martin. Transport Theory. Hoboken, NJ: Wiley, 1979. ISBN: 9780471044925.
Carter, L. L., and E. D. Cashwell. ParticleTransport Simulation with the MonteCarlo Method. TID26607, ERDA Critical Review Series, U. S. Energy Research and Development Administration, Technical Information Center, Oak Ridge, TN, 1975.
Landau, D. P., and K. Binder. A Guide to Monte Carlo Simulations in Statistical Physics. Cambridge, UK: Cambridge University Press, 2000. ISBN: 9780521653664.
Marseguerra, M., and E. Zio. Basics of the Monte Carlo Method with Application to System Reliability. Hagen, Germany: LiLoLeVerlag GmbH, 2002.
"Special Issue on New Frontiers in the Application of Neutron Scattering to Materials Science." MRS Bulletin 28, no. 12 (December 2003).



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