What to expect in a Reactor physics and engineering class

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Discussion Overview

The discussion centers around the topics and expectations for a reactor physics and engineering class within a nuclear engineering concentration. Participants share insights on course content, necessary mathematical skills, and recommended textbooks, focusing on both theoretical and practical aspects of reactor design and analysis.

Discussion Character

  • Exploratory
  • Technical explanation
  • Homework-related
  • Mathematical reasoning

Main Points Raised

  • Some participants outline typical topics covered in a reactor course, including nuclear physics, neutron interactions, fission processes, neutron diffusion, and reactor kinetics.
  • One participant mentions the importance of understanding both homogeneous and heterogeneous reactor designs, as well as safety considerations such as reactivity coefficients and loss-of-coolant accidents (LOCAs).
  • There is a consensus that a strong foundation in solving ordinary differential equations (ODEs) and partial differential equations (PDEs) is crucial, with specific emphasis on diffusion equations with source and sink terms.
  • Participants note that the course may involve analytical problems that are not very mathematically diverse, primarily based on conservation principles.
  • Several participants recommend "Nuclear Reactor Analysis" by J. J. Duderstadt and J. R. Lamarsh, as well as "Introduction to Reactor Theory" by J. R. Lamarsh, which is described as a classic text still widely used despite its age.

Areas of Agreement / Disagreement

Participants generally agree on the foundational topics and mathematical skills necessary for the course, but there is no explicit consensus on the specific course structure or emphasis on certain areas. Some differences in personal experiences and expectations are noted.

Contextual Notes

Participants mention that the intensity of the course may vary, which could affect the emphasis on certain mathematical techniques or topics. The discussion reflects a range of experiences and expectations regarding the course content.

Who May Find This Useful

Students preparing for a nuclear engineering concentration, educators in reactor physics, and professionals interested in the foundational aspects of reactor design and analysis.

koab1mjr
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Hi

My school started a nuclear engineering concentration in the ME/CHE department for the spring and I just wanted to know what are the topics covered typically in a reactor course and what stuff should I brush up on to be sharp for the class?

Thanks in advance.
 
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Does one know the textbook for the class?

Typically, one covers a brief review of nuclear physics. Then one covers neutrons interactions with matter and the concept of cross-sections. Following this, one explores the fission process and then neutron diffusion. One might be exposed to transport theory from which diffusion theory is developed.

With familiarity with neutron diffusion theory, one then explore moderation without absorption and then with absorption (sink) and fission (source). Since commercial reactors, and most other reactors in use, are LWRs, one will likely cover low-energy (thermal) neutron systems. Fast reactors are usually covered later in a separate course.

The latter part of the course would then cover various reactor configurations to which one applies the diffusion theory. One would probably start with homogeneous systems and then move on to heterogenous systems (fuel is separate for coolant and moderator). Likely the course finishes with reactor kinetics and reactivity control.
 
My introduction course was very similar to Astronuc's description with one main exception. After covering homogenous and heterogenous reactors. We then started discussing the merits of many different designs form technical and safety standpoints (reactivity coefficents, inherent and active safty, LOCA's). We even discuessed a small amount of reactor dynamics and control theory.

In my opinion the most demanding part of the course came from the heavy math involved. There was everything from ODE's, PDE's, coupled systems and control theory. If you do want to get a head start, I would suggest learning to solve diffusion equations with source and sink terms for various geometries, although depending on the intesity of the course this may not be emphasized.
 
In an introductory course, a lot of the work will be analytical.

From my experiences, the most important thing to know is how to solve ODE's and PDE's. But to be honest, analytical problems in nuclear engineering aren't very mathematically diverse. Said problems will always fall under...

1st order ODE, which can always be solved by integrating factor (ref. radioactive decay, slowing down theory)
2nd order ODE, which usually comes in the Helmholtz form (ref. diffusion problems)
Simple PDE's, which can be solved by separation of variables

And they aren't very physically diverse either, as most equations will arise from simple conservation principles.

Check out "Nuclear Reactor Analysis" by J. J. Duderstadt and J. R. Lamarsh's two nuclear books. These are common references in reactor physics courses.
 
sounds good. The textbook we are using is the intro to reactor theory by J. R. Lamarsh
its an old book from like 1966
 
koab1mjr said:
sounds good. The textbook we are using is the intro to reactor theory by J. R. Lamarsh
its an old book from like 1966

It may be old but it is the 'classic' that is almost always used for the intro course. The basics haven't really changed since 1966. There are probably 20 copies of this book within 100 feet of where I'm sitting (offices of a large US based reactor vendor).
 

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