22
Views
1
CrossRef citations to date
0
Altmetric
Technical Paper

Reactivity, Isotopic, and Thermal Steady-State Analysis of Homogeneous Thoria-Urania Fuel

, &
Pages 97-110 | Published online: 13 May 2017

  • J. S. HERRING, P. E. MacDONALD, K. D. WEAVER, and C. KULLBERG, “Low Cost, Proliferation Resistant, Uranium-Thorium Dioxide Fuels for Light Water Reactors,” Nucl. Eng. Des., 203, 1, 65 (Jan. 2001).
  • K. D. WEAVER, J. S. HERRING, C. KULLBERG, and P. E. MacDONALD, “Analysis of Thorium-Uranium Fuel Using MOCUP and SCALE,” Trans. Am. Nucl. Soc., 81, 61 (1999).
  • E. P. LOEWEN, P E. MacDONALD, and J. K. HOHORST, “Thoria-Urania Fuel Performance Comparisons Using Frapcon-3 Augmented with ThO2 Material Property Correlations,” Proc. Int. Topl. Mtg. Light Water Reactor Fuel Performance, Park City, Utah, April 10–13, 2000, American Nuclear Society (2000) (CD-Rom).
  • J. BELLE and R. M. BERMAN, “Thorium Dioxide: Properties and Nuclear Applications,” DOE/NE-0060, DE85 006670, U.S. Department of Energy, Naval Reactors Office (1984).
  • SCDAP/RELAP5 DEVELOPMENT TEAM, “SCDAP/RELAPS/MOD 3.2 Code Manual: MATPRO—A Library of Materials Properties for Light Water Reactor Accident Analysis,” NUREG/CR-6150, Vol. 4, Rev. 1, INEEL-96/0422, Idaho National Engineering and Environmental Laboratory (1996).
  • E. P. LOEWEN, P. E. MacDONALD, J. K. HOHORST, J. P. SHARPE, and L. SIEFKEN, “Development of Material Property Correlations for Analysis of Mix Thoria-Urania Fuel Performance in Light Water Reactors and Augmentation of the FRAPCON-3 Computer Code,” INEEL/EXT-2000-00275, Idaho National Engineering and Environmental Laboratory (Aug. 2000).
  • Y. YUAN, P. MONNIER, C. S. RIM, and M. S. KAZIMI, “Fission Gas Release Modeling for Thoria-Urania Fuels: A Preliminary Investigation,” MIT-NFC-TR-022, Massachusetts Institute of Technology, Department of Nuclear Engineering (Sep. 2000).
  • R. L. MOORE, B. G. SCHNITZLER, C. A. WEMPLE, R. S. BABCOCK, and D. E. WESSOL, “MOCUP: MCNP-ORIGEN2 Coupled Utility Program,” INEL-95/0523, Idaho National Engineering Laboratory (Sep. 1995).
  • “MCNP—A General Monte Carlo N-Particle Transport Code,” Version 4B, J. F. BRIESMEISTER, Ed., Los Alamos National Laboratory (1997).
  • A. G. CROFF, “A User’s Manual for the ORIGEN2 Computer Code,” Version 2.1, Oak Ridge National Laboratory (1980).
  • X. ZHAO, E. E. PILAT, K. D. WEAVER, and P. HEJZLAR, “A PWR Thorium Unit Cell Burnup Benchmark,” Proc. Int. Topl. Mtg. Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), Pittsburgh, Pennsylvania, May 7–12, 2000, American Nuclear Society (2000) (CD-Rom).
  • X. ZHAO, K. D. WEAVER, Y. XU, and T. J. DOWNAR, “Comparison of Computer Code Predictions for ThO2 Pin Cell Burnup,” Trans. Am. Nucl. Soc., 83, 197 (2000).
  • M. J. DRISCOLL, T. J. DOWNAR, and E. E. PILAT, The Linear Reactivity Model for Nuclear Fuel Management, American Nuclear Society, La Grange Park, Illinois (1990).
  • “Method for Calculating the Fractional Release of Volatile Fission Products from Oxide Fuel,” ANSI/ANS-5.4-1982, American Nuclear Society (1982) (a historical standard).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.