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Nuclear reactor physics by Weston Stacey

  1. Apr 17, 2006 #1


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    "nuclear reactor physics" by Weston Stacey

    I just bought it and started reading it. Anybody know the book ? Opinions, remarks ? I might have a few questions when reading it, are some people prepared to discuss it ?

    As a first question, actually, on the cross section plots, there's always something like MT = 18 (for instance, page 7 already) or MT = 27 or the like. What does it mean ? Some kind of temperature ?

  2. jcsd
  3. Apr 17, 2006 #2
    I am familiar with the book, only because Professor Stacey is the only professor who does research with fusion here. I asked him a question one time and after he answered me, he said I could find out more in his book.

    I think MT refers to the macroscopic total cross section, as in totaling the fission, absorpion, and scattering cross sections.
  4. Apr 17, 2006 #3


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    The data for the cross sections in Stacey's textbook originate from the Cross Section Evaluation Working Group (CSEWG) at Brookhaven National Lab (BNL). The MF and MT designations may be designations of data types or fields. They seem to be used in ENDF cross-section files.

    BTW the BNL site links in Stacey's book are no longer valid.

    Use - http://www.nndc.bnl.gov/csewg/ for the CSEWG, where you will find some information on Cross Section libraries and contact information. On this site, look on right side at top for - ENDF-6 Formats and Procedures Manual (ENDF-102) (PDF). This file (18.5 MB) contains a description of the nomenclature:

    For other inquiries use - http://www.nndc.bnl.gov

    Stacey's book is for more advanced classes in reactor theory, usually first year graduate class in reactor theory.
    Last edited: Apr 17, 2006
  5. Apr 17, 2006 #4
    Nevermind me, I was guessing from context. That file says that MT = 27 is rarely used though. I still cannot see how they get a number from a reaction, what an odd system!
  6. Apr 17, 2006 #5


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    From Appendix A, Glossary, of the ENDF-102 Data Formats and Procedures (pdf) document, MT is the "Reaction type number, or, covariance file section identifier."

    Looking in Appendix B:

    MT=18 is the fission cross-section.

    MT=27 is the Absorption cross-section; sum of MT=18 and MT=102 through MT=117. Comment: rarely used.

    Basically ENDF is used to generate macroscopic cross-sections with the appropriate codes.

    The pdf document is 345 pages.
  7. Apr 18, 2006 #6


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    Astronuc, thanks a lot ! I would never have found that out on my own :bugeye: (indeed, the link in the book is defective, thanks for providing an update on that too). Ok, Stacey could have said in a footnote what it was, no ?
    Because finding an appendix on a 300+ pdf file on a server which is specified with a defective link is maybe not directly the most obvious way to understand this!

    I'll be back with questions on the book I guess...

  8. Apr 18, 2006 #7
    If you haven't seen it, this is a pretty useful site for looking up cross-section information:


    Go to the nuclide you want, click on cross-section (XS) graphs, select the ENDF, and you can plot any of the categories (MT=whatever) you want. You can also download the data points into a text file if you need to use it in a computer program.
  9. May 21, 2006 #8
  10. Feb 20, 2009 #9
    Re: "nuclear reactor physics" by Weston Stacey

    hi all
    plz if anyone have the manual for this book because i need it to solve the problems for this book
  11. Feb 20, 2009 #10


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    Re: "nuclear reactor physics" by Weston Stacey

    We don't provide such things here.
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