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Technical Paper

Monte Carlo Analysis of the Effects of a Blanket-Shield Penetration on the Performance of a Tokamak Fusion Reactor

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Pages 65-72 | Published online: 10 May 2017

References

  • T. IDE, Y. SEKI, and H. IIDA, “Effects of Neutron Streaming Through Injection Ports on Neutronic Characteristics of a Fusion Reactor,” Proc. 2nd Topl. Mtg. Technology of Controlled Nuclear Fusion, Richland, Washington, September 21–23, 1975, Vol. II, p. 395.
  • M. A. ABDOU, L. J. MILTON, J. C. JUNG, and E. M. GELBARD, “Multidimensional Neutronic Analysis of Major Penetrations in Tokamaks,” Proc. 2nd Topl. Mtg. Technology of Controlled Nuclear Fusion, Richland, Washington, September 21–23, 1975, Vol. II, p. 845.
  • M. B. EMMETT, “The MORSE Monte Carlo Radiation Transport Code System,” ORNL 4972, Oak Ridge National Laboratory (1975).
  • M. ROBERTS and E. S. BETTIS, “Oak Ridge Tokamak Experimental Power Reactor Study Reference Design,” ORNL/TM-5042, Oak Ridge National Laboratory (1975).
  • R. T. SANTORO, V. C. BAKER, and J. M. BARNES, “Neutronics and Photonics Calculations for the Tokamak Experimental Power Reactor,” ORNL/TM-5466, Oak Ridge National Laboratory (1977).
  • W. W. ENGLE, Jr., “A User’s Manual for ANISN, A One-Dimensional Discrete Ordinates Code with Anisotropic Scattering,” K-1693, Computing Technology Center, Union Carbide Corporation (1967).
  • G. L. KULCINSKI et al., “A Method to Reduce the Effects of Plasma Contamination and First-Wall Erosion in Fusion Reactors,” UWFDM-108, University of Wisconsin (1974).
  • G. E. HANSEN and H. A. SANDMEIER, “Neutron Penetration Factors Obtained by Using Adjoint Transport Calculations,” Nucl. Sci. Eng., 22, 315 (1965).
  • D. M. PLASTER, R. T. SANTORO, and W. E. FORD III, “Coupled 100-Group Neutron and 21-Group Gamma-Ray Cross Sections for EPR Calculations,” ORNL/TM-4872, Oak Ridge National Laboratory (1975).
  • W. E. FORD III, R. T. SANTORO, R. W. ROUSSIN, and D. M. PLASTER, “Modification Number One to the Coupled 100n-21γ Cross-Section Library for EPR Calculations,” ORNL/TM-5249, Oak Ridge National Laboratory (1976).
  • M. A. ABDOU, C. W. MAYNARD, and R. Q. WRIGHT, “MACK—A Computer Program to Calculate Neutron Energy Release Parameters (Fluence-to-Kerma Factors) and Multigroup Neutron Reaction Cross Sections from Nuclear Data in ENDF Format,” ORNL/TM-3994, Oak Ridge National Laboratory (1973).
  • N. M. GREENE et al., “AMPX: A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B,” ORNL/TM-3706, Oak Ridge National Laboratory (1976).
  • T. A. GABRIEL, J. D. AMBURGEY, and N. M. GREENE, “Radiation-Damage Calculations: Primary Knock-On Atom Spectra, Displacement Rates, and Gas Production Rates,” Nucl. Sci. Eng., 61, 21 (1976).

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