Argonne National Laboratory
Reduced Enrichment for Research and Test Reactors
Nuclear Science and Engineering Division at Argonne
U.S. Department of Energy

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RERTR Publications:
Foreign Research Reactor Spent Nuclear Fuel


  1. J. R. Deen, W. L. Woodruff and C.I. Costescu, "WIMS-D4M User Manual (Rev. 0)," ANL/RERTR/TM-23, Argonne National Laboratory, Argonne, IL (July 1995).
  2. J. E. Matos, "Foreign Research Reactor Irradiated Nuclear Fuel Inventories Containing HEU And LEU Of United States Origin," ANL/RERTR/TM-22, Argonne National Laboratory, Argonne, IL (December 1994).
  3. R. B. Pond and J. E. Matos, "Photon Dose Rates From Spent Fuel Assemblies With Relation To Self-Protection (Rev. 1)," ANL/RERTR/TM-25, Argonne National Laboratory, Argonne, IL (February 1996); see also, Internet site
  4. A. M. Weinberg and E. P. Wigner, "The Physical Theory Of Neutron Chain Reactors," p. 133, University of Chicago Press, Chicago, IL (1958).
  5. S. Glasstone, "Principles Of Nuclear Reactor Engineering," p. 118, D. Van Nostrand Company, Princeton, NJ (1955).
  6. H. Etherington, Ed., "Nuclear Engineering Handbook," p. 7-15, McGraw-Hill Book Company, New York, NY (1958).
  7. K. Way and E. P. Wigner, "The Rate Of Decay Of Fission Products," Phys. Rev., 73, 1318 (1948).
  8. K. Way and E. P. Wigner, "Radiation From Fission Products," Phys. Rev., 70, 115 (1946).
  9. M. J. Bell, "ORIGEN - The ORNL Isotope Generation And Depletion Code," ORNL-4628, Oak Ridge National Laboratory, Oak Ridge, TN (May 1973).
  10. M. M. El-Wakil, "Nuclear Heat Transport," p. 94, International Textbook Company, Scranton, PA (1971).
  11. "Reactor Physics Constants," ANL-5800, p. 634, Argonne National Laboratory, Argonne, IL (July 1963).
  12. S. Untermyer and J. T. Weills, "Heat Generation In Irradiated Uranium," ANL-4790, Argonne National Laboratory, Argonne, IL (February 1952).
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Last modified on July 29, 2008 11:34 +0200