DOC PREVIEW
MIT 22 06 - Problem Set #2

This preview shows page 1 out of 2 pages.

Save
View full document
View full document
Premium Document
Do you want full access? Go Premium and unlock all 2 pages.
Access to all documents
Download any document
Ad free experience
Premium Document
Do you want full access? Go Premium and unlock all 2 pages.
Access to all documents
Download any document
Ad free experience

Unformatted text preview:

22.06 ENGINEERING OF NUCLEAR SYSTEMS - Fall 2010 Problem Set 2 Reactor Physics Review + Thermal Parameters Reference Textbooks:[RAK] = Knief, R. A. Nuclear Engineering: Theory and Technology of Commercial Nuclear Power2nd ed. La Grange Park, IL: ANS, 2008. ISBN: 9780894484582.1) A spherical reactor composed of U-235 metal is operating in a critical steady state. Using the keff formula derived in class as your guide, discuss what probably happens to the multiplication factor of the reactor and why, if the system is modified in the following ways (treat each modification separately, not cumulatively): (a) an overweight operator accidentally sits on the reactor, squashing it into an ellipsoidal shape, (b) a sheet of cadmium is inserted in the reactor, (c) another identical reactor is placed a short distance from the original reactor, and (d) one simply leaves the reactor alone for a period of time. 2) What is the maximum value of the multiplication factor that can be achieved in any conceivable reactor design which uses U-235 as its fuel? What if one uses Pu-239 fuel? Useful information for this problem: Isotope Neutrons emitted per fission, 4) Given the results in Problem 3 above, why is light water such a popular moderator? 5) [RAK] Chapter 7, Problem 7-5 6) [RAK] Chapter 7, Problem 7-10 Fission cross section Capture cross  (b) section (b) Thermal Fast Thermal Fast Thermal Fast U-235 2.43 2.65 577 1.4 101 0.25 Pu-239 2.87 3.15 741 1.8 274 0.26 (Adapted from Duderstadt and Hamilton text.)(Adapted from Duderstadt and Hamilton text.) 3) Consider an infinitely large homogeneous mixture of U-235 and a moderating material. Determine the fuel-to-moderator ratio (i.e. ratio of number densities) that will render this system critical for the following moderators: (a) graphite, (b) beryllium, (c) water (H2O), and (d) heavy water (D2O). Assume f = 577 b and a = 678 b for U-235 + use the thermal cross section data given in the table below for H2O, D2O, Be and C. (Adapted from Duderstadt and Hamilton text.)Useful Reference - Table: 2200m/sec CROSS SECTIONS FOR NATURALLY OCCURRING ELEMENTS [From Reactor Physics Constants, ANL-5800 (1963)].Duderstadt, J. J., and L. J. Hamilton. Nuclear Reactor Analysis. Hoboken, NJ: John Wiley & Sons, Inc., 1976. ISBN: 9780471223634.MIT OpenCourseWarehttp://ocw.mit.edu 22.06 Engineering of Nuclear Systems Fall 2010 For information about citing these materials or our Terms of Use, visit:


View Full Document

MIT 22 06 - Problem Set #2

Download Problem Set #2
Our administrator received your request to download this document. We will send you the file to your email shortly.
Loading Unlocking...
Login

Join to view Problem Set #2 and access 3M+ class-specific study document.

or
We will never post anything without your permission.
Don't have an account?
Sign Up

Join to view Problem Set #2 2 2 and access 3M+ class-specific study document.

or

By creating an account you agree to our Privacy Policy and Terms Of Use

Already a member?