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Technical Paper

Preliminary Neutronics Calculations for Conversion of the Tehran Research Reactor Core from Heu to Leu Fuel

Pages 187-198 | Published online: 12 May 2017

References

  • “Research Reactor Core Conversion from the Use of Highly Enriched Uranium to the Use of Low Enriched Uranium Fuels-Guidebook,” IAEA-TECDOC-223, International Atomic Energy Agency (1980).
  • “Research Reactor Core Conversion from the Use of Highly Enriched Uranium to the Use of Low Enriched Uranium Fuels — Guidebook Addendum on Heavy-Water-Moderated Reactors,” IAEA-TECDOC-324, International Atomic Energy Agency (Jan. 1985).
  • E. YILMAZ and B. G. JONES, “Selection and Benchmarking of Computer Codes for Research Reactor Core Conversions,” ANL/RERTR/TM-4, p. 654, Argonne National Laboratory (1982).
  • J. A. RATHKOFF, C. R. DRUMM, W. R. MARTIN, and J. C. LEE, “Analysis of the Ford Nuclear Reactor LEU Core,” ANL/RERTR/TM-4, p. 377, Argonne National Laboratory (1982).
  • E. T. DUGAN, G. S. KNIEDLER, and N. J. DIAZ, “Neutronic Calculations for the Conversion of the University of Florida Training Reactor from HEU to LEU Fuel,” ANL/RERTR/TM-4, p. 627, Argonne National Laboratory (1982).
  • M. CANER and T. ALDEMIR, “Preliminary Neutronics Calculations for the OSURR LEU Conversion/Upgrade Program,” Reduced Enrichment for Research and Test Reactors, p. 273, P. VON DER HARDT and A. TRAVELLI, Eds., D. Reidel Publishing, Hingham, Massachusetts (1986).
  • D. C. LOSEY, F. B. BROWN, W. R. MARTIN, and J. C. LEE, “Core Physics Analysis in Support of the FNR HEU-LEU Demonstration Experiment,” ANL/RERTR/TM-3, p. 450, Argonne National Laboratory (1980).
  • R. F. BARRY, “LEOPARD-A Spectrum Dependent Non-Spatial Depletion Code for the IBM-7094,” WCAP-3269-26, Westinghouse Electric Corporation (1963).
  • A. SHAPIRO, H. C. HURIA, and K. W. CHO, “VENTURE/pc—A Multidimensional Multigroup Neutron Diffusion Code System, Version 2,” EGG-2582, Idaho National Engineering Laboratory (1990).
  • T. B. FOWLER, D. R. VONDY, and G. W. CUNNINGHAM, “Nuclear Reactor Core Analysis Code: CITATION,” ORNL-TM-2496, Rev. 2, Oak Ridge National Laboratory (July 1971).

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