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Nuclear Technology Volume 111, 1995 - Issue 2: Nuclear Criticality Safety Special
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Technical Paper

Validation of KENO V.a with ENDF/B-V Cross Sections for 233U Systems

M. E. DunnUniversity of Tennessee, Nuclear Engineering Department Knoxville, Tennessee 37996-2300
,
B. BasogluUniversity of Tennessee, Nuclear Engineering Department Knoxville, Tennessee 37996-2300
,
C. L. BentleyUniversity of Tennessee, Nuclear Engineering Department Knoxville, Tennessee 37996-2300
,
C. HaughtMartin Marietta Energy Systems, Building X-710 Mail Stop 2213, P.O. Box 628, Piketon, Ohio 45661
,
M. J. PlasterUniversity of Tennessee, Nuclear Engineering Department Knoxville, Tennessee 37996-2300
,
A. D. WilkinsonUniversity of Tennessee, Nuclear Engineering Department Knoxville, Tennessee 37996-2300
,
T. YamamotoJapan Atomic Energy Research InstituteDepartment of Fuel Cycle Safety Research Tokai-mura, Naka-gun, Ibariken 319-11, Japan
&
H. L. DoddsUniversity of Tennessee, Nuclear Engineering Department Knoxville, Tennessee 37996-2300
 show all
Pages 183-196 | Published online: 10 May 2017

References

  • R. T. PRIMM III, “Criticality Safety Studies of Building 3019 Cell 4 and In-Line Storage Wells,” ORNL/TM-12374, Oak Ridge National Laboratory (1993).
  • “SCALE: A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation,” NUREG/CR-0200, Vols. 1-5, U.S. Nuclear Regulatory Commission (revisited and reissued Jan. 1990).
  • L. M. PETRIE and N. F. LANDERS, “KENO V.a: An Improved Monte Carlo Criticality Program with Super-grouping,” NUREG/CR-0200, Vol. 2, Sec. Fll, ORNL/NUREG/CSD-2/Vl/Rl, Oak Ridge National Laboratory (Dec. 1984).
  • S. M. BOWMAN, R. Q. WRIGHT, H. TANIUCHI, and M. D. DeHART, “Validation of Scale-4 Criticality Sequences Using ENDF/B-V Data,” Proc. Topi. Mtg. Physics and Methods in Criticality Safety, Nashville, Tennessee, September 19-23, 1993, 188, American Nuclear Society (1993).
  • J. K. FOX, L. W. GILLEY, and E. R. ROHRER, “Critical Mass Studies Part VIII Aqueous Solutions of 233U,” ORNL-2143, Oak Ridge National Laboratory (1959).
  • J. T. THOMAS, J. K. FOX, and D. CALLIHAN, “A Direct Comparison of Some Nuclear Properties of U-233 and U-235,” Nucl. Sci. Eng., 1, 20 (1956).
  • R. GWIN and D. W. MAGNUSON, “The Measurement of Eta and Other Nuclear Properties of U233 and U235 in Critical Aqueous Solutions,” Nucl. Sci. Eng., 12, 364 (1962).
  • J. D. JENKINS and S. R. McNEANY, “Criticality Considerations for 233U Fuels in an HTGR Fuel Refabrication Facility,” ORNL/TM-6136, Oak Ridge National Laboratory (1978).
  • H. C. PAXTON and N. L. PRUVOST, “Criticality Dimensions of Systems Containing 235U, 239Pu, and 233U, 1986 Revision,” LA-10860-MS, Los Alamos National Laboratory (1986).
  • J. T. THOMAS, “Criticality of 233U Aqueous Nitrate Solution in Reflected and Unreflected Arrays,” Trans. Am. Nucl. Soc., 10, 538 (1967).

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