Cross-Section Sensitivity Study for the Toroidal Field Coil Shielding Parameters in the ITER/OTR Design

References

• E. A. STRAKER, “Sensitivity of Secondary Gamma-Ray Dose to Angular Distribution of Gamma Rays from Neutron Inelastic Scattering,” Nucl. Sci. Eng., 41, 147 (1970).
   Web of Science ®Google Scholar
• D. E. BARTINE et al., “Cross-Section Sensitivity of Breeding Ratio in a Fusion Reactor Blanket,” Nucl. Sci. Eng., 53, 304 (1974).
   Web of Science ®Google Scholar
• C. R. WEISBIN et al., “Cross-Section and Method Uncertainties: The Application of Sensitivity Analysis to Study Their Relationship in Radiation Transport Benchmark Problem,” ORNL/TM-4847, Oak Ridge National Laboratory (1975).
   Google Scholar
• C. R. WEISBIN et al., “Application of FORSS Sensitivity and Uncertainty Methodology to Fast Reactor Benchmark Analysis,” ORNL/TM-5563, Oak Ridge National Laboratory (1976).
   Google Scholar
• M. A. ABDOU et al., “Deuterium-Tritium Fuel Self-Sufficiency in Fusion Reactors,” Fusion Technol., 9, 250 (1986).
   Web of Science ®Google Scholar
• S. PELLONI and E. T. CHENG, “Cross-Section Sensitivity Study for U.S. Fusion Engineering Device (FED),” Nucl. Technol., 4, 841 (1983).
   Web of Science ®Google Scholar
• M. Z. YOUSSEF et al., “Impact of Cross-Section Uncertainties on the Nuclear Design of Hybrid Reactors,” Nucl. Technol., 4, 648 (1983).
   Google Scholar
• M. Z. YOUSSEF et al., “Error Estimates of Fissile Fuel and Tritium Production in the SOLASE-H Hybrid Reactor,” Trans. Am. Nucl. Soc., 34, 33 (1980).
   Google Scholar
• S. A. GERSTL et al., “Cross-Section Sensitivity and Uncertainty Analysis with Application to a Fusion Reactor,” Nucl. Sci. Eng., 62, 137 (1977).
   Web of Science ®Google Scholar
• S. A. GERSTL et al., “A Comprehensive Neutron Cross-Section and Secondary Energy Distribution Uncertainty Analysis for a Fusion Reactor,” LA-8333-MS, Los Alamos National Laboratory (1980).
   Google Scholar
• R. G. ALSMILLER et al., “Comparison of the Cross Section Sensitivity of the Tritium Breeding Ratio in Various Fusion-Reactor Blankets,” Nucl. Sci. Eng., 57, 122 (1975).
   Web of Science ®Google Scholar
• Y. SEKI et al., “Macroscopic Cross-Section Sensitivity Study for Fusion Shielding Experiments,” ORNL/TM-5467, Oak Ridge National Laboratory (1978).
   Google Scholar
• Y. SEKI et al., “Comparison of One- and Two-Dimensional Cross-Section Sensitivity Calculations for a Fusion Reactor Shielding Experiment,” ORNL/TM-6667, Oak Ridge National Laboratory (1979).
   Google Scholar
• M. Z. YOUSSEF and M. A. ABDOU, “Uncertainties in Prediction of Tritium Breeding in Candidate Blanket Designs Due to Present Uncertainties in Nuclear Data Base,” Fusion Technol., 9, 286 (1986).
   Web of Science ®Google Scholar
• Y. OKA, K. FURUTA, and S. KONDO, “Fusion Nuclear Systems Design and Analysis,” Fusion Eng. Des., 7, 369 (1989).
   Web of Science ®Google Scholar
• K. FURUTA, Y. OKA, and S. KONDO, “Development of Method Based on Perturbation Theory for Estimating and Correcting Errors in Numerical Solution of Transport Equation,” J. Nucl. Sci. Technol., 24, 3 173 (1987).
   Web of Science ®Google Scholar
• K. A. VERSCHUUR, “Uncertainties in Shielding Calculations,” presented at ITER Specialist Meeting on Shield/Blanket/First Wall Design Concepts and Tritium Breeding Materials, Garching, Germany, June 13–17, 1988.
   Google Scholar
• R. G. ALSMILLER, J. BARISH, and C. R. WEISBIN, “Uncertainties in Calculated Heating and Radiation Damage in the Toroidal Field Coil of a Tokamak Experimental Power Reactor Due to Neutron Cross-Section Errors,” Nucl. Technol., 34, 376 (1977).
   Web of Science ®Google Scholar
• A. I. ILUJSHKIN et al., “The Influence of Uncertainty of Neutron Cross Sections on the Thermonuclear Reactor Blanket and Shield Characteristics Investigation Energiya, 56, 1 (1984) (in Russian).
   Web of Science ®Google Scholar
• A. SANTAMARINA and H. J. SMITH, “Sensitivity Analysis of the TF Coil Shielding Parameters in the NET Design, to the Nuclear Data Uncertainties,” EFF-DOC-73, Commissariat à l’Energie Atomique (1991).
   Google Scholar
• T. PARISH and A. SANTAMARINA, “Sensitivity and Uncertainty Analysis of the NET Magnet Neutronic Design Parameters to Uncertainties in Cross-Section Data,” Final Report and EFF-DOC-136, Commissariat à l’Energie Atomique (1991).
   Google Scholar
• A. HOGENBIRK, “New Sources of Uncertainties in Sensitivity/Uncertainty Studies,” presented at 17th Symp. Fusion Technology, Rome, Italy, September 14–18, 1992.
   Google Scholar
• V. V. ORLOV, “The Design of an Experimental Thermonuclear Reactor,” VANT, 2, 3 (1986) (in Russian).
   Google Scholar
• D. SMITH et al., “ITER Blanket and Material Data Base,” ITER Documentation Series, No. 29, International Atomic Energy Agency (1991).
   Google Scholar
• A. J. GLASS, “Status and Plans for ITER,” J. Fusion Energy, 11, 2 59 (1992).
   Web of Science ®Google Scholar
• P. H. REBUT, “The ITER Challenge,” presented at 17th Conf. Fusion Technology, Rome, Italy, September 14–18, 1992.
   Google Scholar
• D. E. BARTINE, F. R. MYNATT, and E. M. OBLOW, “SWANLAKE, A Computer Code Utilizing ANISN Radiation Transport Calculations for Cross Section Sensitivity Analysis,” ORNL-TM-3809, Oak Ridge National Laboratory (1973).
   Google Scholar
• W. W. ENGLE, “A User’s Manual for ANISN; a One-Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering,” K-1693, Union Carbide Corporation (1967).
   Google Scholar
• “VITAMIN-C: 171 Neutron, 36 Gamma Group Cross Section Library in AMPX Interface Format for Fusion Neuronics Studies,” DLC-41, Oak Ridge National Laboratory (1978).
   Google Scholar
• S. ZIMIN, “A Study on Radiation Shielding Analysis for Toroidal Field Coils of a Tokamak-Type Fusion Reactor,” JAERI-M 92-120, Japan Atomic Energy Research Institute (Aug. 1992).
   Google Scholar
• D. G. DORAN and N. J. GRAVES, “Neutron Displacement Damage Cross Section for Structural Metals,” HEND-SA1058, Hanford Engineering Development Laboratory (1976).
   Google Scholar
• “TCT. Two Component Torus Joint Conceptual Design Study,” Vol. 3, Princeton Plasma Physics Laboratory and Westinghouse Electric Corporation (1978).
   Google Scholar
• U. FISCHER, “Qualification of Neutronic Blanket and Shielding Calculations in a One-Dimensional Approach to a Tokamak Reactor,” Fusion Technol., 22, 251 (1992).
   Web of Science ®Google Scholar
• A. B. PASHCHENKO and D. W. MUIR, “FENDL-2 and Associated Benchmark Calculations,” Summary Report of the Advisory Group Mtg., Vienna, Austria, November 18–22, 1991, INDC(NDS)-260, International Atomic Energy Agency (1991).
   Google Scholar
• “Nuclear Data for Fusion Reactor Technology,” Proc. Advisory Group Mtg. Nuclear Data for Fusion Reactor Technology, Vienna, Austria, December 11–15, 1978, IAEA-TECDOC-223, International Atomic Energy Agency (1978).
   Google Scholar
• “ WRENDA 83/84. World Request List for Nuclear Data,” International Atomic Energy Agency (Nov. 1983).
   Google Scholar