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Nuclear Science and Engineering Volume 161, 2009 - Issue 1
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Technical Paper

Reducing Parasitic Thermal Neutron Absorption in Graphite Reactors by 30%

C. D. BowmanADNA Corporation, 1045 Los Pueblos, Los Alamos, New Mexico 87544
,
E. G. BilpuchTriangle Universities Nuclear Laboratory, Duke University, Durham, North Carolina 27708
,
D. C. BowmanADNA Corporation, 1045 Los Pueblos, Los Alamos, New Mexico 87544
,
A. S. CrowellTriangle Universities Nuclear Laboratory, Duke University, Durham, North Carolina 27708
,
C. R. HowellTriangle Universities Nuclear Laboratory, Duke University, Durham, North Carolina 27708
,
K. McCabeADNA Corporation, 1045 Los Pueblos, Los Alamos, New Mexico 87544
,
G. A. SmithADNA Corporation, 1045 Los Pueblos, Los Alamos, New Mexico 87544
,
A. P. TonchevTriangle Universities Nuclear Laboratory, Duke University, Durham, North Carolina 27708
,
W. TornowTriangle Universities Nuclear Laboratory, Duke University, Durham, North Carolina 27708
,
V. VioletTriangle Universities Nuclear Laboratory, Duke University, Durham, North Carolina 27708
,
R. B. VogelaarVirginia Polytechnic Institute and State University, Blacksburg, Virginia 24061
,
R. L. WalterTriangle Universities Nuclear Laboratory, Duke University, Durham, North Carolina 27708
&
J. YinglingADNA Corporation, 1045 Los Pueblos, Los Alamos, New Mexico 87544
 show all
Pages 68-77 | Published online: 10 Apr 2017

References

  • C. D. BOWMAN, “Accelerator-Driven Systems for Nuclear Waste Transmutation,” Ann. Rev. Nucl. Part. Sci., 48, 505 (1998); see also C. D. BOWMAN, “Once-Through Thermal-Spectrum Accelerator-Driven Light Water Reactor Waste Destruction Without Reprocessing,” Nucl. Technol., 132, 66 (2000).
  • C. D. BOWMAN, “Accelerator-Driven Waste Transmutation and Nuclear Energy Production from Thorium Without Reprocessing and Recycling,” Proc. Int. Conf. Emerging Nuclear Energy Systems (ICENES 2002), Albuquerque, New Mexico, September 29–October 4, 2002, National Technical Information Service (2002).
  • C. D. BOWMAN, D. C. BOWMAN, T. HILL, J. LONG, A. P. TONCHEV, W. TORNOW, F. TROUW, S. VOGEL, R. L. WALTER, S. WENDER, and V. YUAN, “Measurements of Thermal Neutron Diffraction and Inelastic Scattering in Reactor-Grade Graphite,” Nucl. Sci. Eng., 159, 182 (2008).
  • S. GLASSTONE and M. C. EDLUND, The Elements of Nuclear Reactor Theory, pp. 116–127, D. Van Nostrand Company, New York (1952)
  • ARGONNE NATIONAL LABORATORY, Reactor Physics Constants, ANL-5800, 2nd ed., p. 106, U. S. Atomic Energy Commission (1963).
  • S. F. MUGHABGHAB, M. DIVADEENAM, and N. E. HOLDEN, Neutron Cross Sections, Vol. 1, Part A, Academic Press, New York (1981).
  • B. CUTTS, “Steady State Reactor Physics,” The Design of Gas-Cooled Graphite-Moderated Reactors, p. 34, Oxford University Press, New York (1963).

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