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Fusion Science and Technology Volume 61, 2012 - Issue 1T
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Fission

Monitoring Spent or Reprocessed Nuclear Fuel Using Fast Neutrons

G. F. ChaplineLawrence Livermore National Laboratory: P.O. Box 808, Livermore, CA 94551, [email protected]
,
L. F. NakaeLawrence Livermore National Laboratory: P.O. Box 808, Livermore, CA 94551, [email protected]
,
N. SnydermanLawrence Livermore National Laboratory: P.O. Box 808, Livermore, CA 94551, [email protected]
,
J. M. VerbekeLawrence Livermore National Laboratory: P.O. Box 808, Livermore, CA 94551, [email protected]
&
R. WurzLawrence Livermore National Laboratory: P.O. Box 808, Livermore, CA 94551, [email protected]
Pages 150-154 | Published online: 10 Aug 2017

References

  • R. P. FEYNMAN, F. DE HOFFMANN, R. SERBER, “Dispersion of the Neutron Emission in U- 235 Fission,” J. of Nuclear Energy 3, 64, (1956).
  • W. HAGE, and D. M. CIFARELLI, “Models for a Three-Parameter Analysis of Neutron Signal Correlation Measurements for Fissile Material Assay,” Nucl. Instr. and Meth. A251, 550 (1986).
  • R. WURTZ et al, “Verification with γ-ray and Fast Neutron Detection,” Proc. of INMM, Baltimore, MD, July 2010, 51, INMM (2010).

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