RERTR Publications:
Foreign Research Reactor Spent Nuclear Fuel
ANL/RERTR/TM-26
REFERENCES
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).
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).
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 http://www.rertr.anl.gov/RERTR/index.html.
A. M. Weinberg and E. P. Wigner, "The Physical Theory
Of Neutron Chain Reactors," p. 133, University of Chicago
Press, Chicago, IL (1958).
S. Glasstone, "Principles Of Nuclear Reactor Engineering,"
p. 118, D. Van Nostrand Company, Princeton, NJ (1955).
H. Etherington, Ed., "Nuclear Engineering Handbook,"
p. 7-15, McGraw-Hill Book Company, New York, NY (1958).
K. Way and E. P. Wigner, "The Rate Of Decay Of Fission
Products," Phys. Rev., 73, 1318 (1948).
K. Way and E. P. Wigner, "Radiation From Fission Products,"
Phys. Rev., 70, 115 (1946).
M. J. Bell, "ORIGEN - The ORNL Isotope Generation And
Depletion Code," ORNL-4628, Oak Ridge National Laboratory,
Oak Ridge, TN (May 1973).
M. M. El-Wakil, "Nuclear Heat Transport," p. 94,
International Textbook Company, Scranton, PA (1971).
"Reactor Physics Constants," ANL-5800, p. 634, Argonne
National Laboratory, Argonne, IL (July 1963).
S. Untermyer and J. T. Weills, "Heat Generation In Irradiated
Uranium," ANL-4790, Argonne National Laboratory, Argonne,
IL (February 1952).
The
2009 International RERTR Meeting (RERTR-2009) was held in
Beijing, China from Nov-1-5, 2009.
For more information visit
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