Nuclear Analysis of Integral Experiments on a Li₂O Test Assembly with Local Heterogeneities Utilizing a 14-MeV Neutron Source

References

• T. Nakamura and M. A. Abdou, “Summary of Recent Results from the JAERI/U.S. Fusion Neutronics Phase I Experiments,” Fusion Technol., 10, 541 (1986).
   Web of Science ®Google Scholar
• M. Z. Youssef et al., “Analysis and Inter Comparison for Phase I Fusion Integral Experiments at the FNS Facility,” Fusion Technol., 10, 549 (1986).
   Web of Science ®Google Scholar
• M. Z. Youssef et al., “Phase I Fusion Integral Experiments, Vol. II: Analysis,” UCLA-ENG-88-15, University of California, Los Angeles (Sep. 1988); see also JAERI-M-88-177, Japan Atomic Energy Research Institute (Aug. 1988).
   Google Scholar
• M. Nakagawa et al., “Analysis of Neutronics Parameters Measured in Phase II Experiments of JAERI/U.S. Collaborative Program on Breeder Neutronics, Part I: Source Characteristics and Reaction Rate Distribution,” Fusion Eng. Des., 9, 315 (1989).
   Web of Science ®Google Scholar
• Y. Oyama et al., “Phase II Experimental Results of JAERI/USDOE Collaborative Program on Fusion Blanket Neutronics Experiments,” Fusion Eng. Des., 9, 309 (1989).
   Web of Science ®Google Scholar
• M. Z. Youssef et al., “Analysis of Neutronics Parameters Measured in Phase II Experiments of the JAERI/U.S. Collaborative Program on Fusion Blanket Neutronics, Part II: Tritium Production and In-System Spectrum,” Fusion Eng. Des., 9, 323 (1989).
   Web of Science ®Google Scholar
• Y. OYAMA et al., “Phase IIB Experiments of JAERI/USDOE Collaborative Program on Fusion Blanket Neutronics,” Fusion Technol., 15, 1293 (1989).
   Web of Science ®Google Scholar
• M. Z. Youssef et al., “Comparative Analysis for Phase IIA and IIB Experiments of the U.S./JAERI Collaborative Program on Fusion Blanket Neutronics,” Fusion Technol., 15, 1299 (1989).
   Web of Science ®Google Scholar
• Y. Ikeda et al., “Determination of Neutron Spectrum in D-T Fusion Field by Foil Activation Technique,” Fusion Technol., 15, 1287 (1989).
   Web of Science ®Google Scholar
• M. Z. Youssef et al., “The U.S./JAERI Collaborative Program on Fusion Neutronics; Phase IIA and IIB Fusion Integral Experiments, The U.S. Analysis,” UCLA-ENG-90-14, University of California, Los Angeles (Dec. 1989).
   Google Scholar
• M. Nakagawa et al., “JAERI/U.S. Collaborative Program on Fusion Blanket Neutronics, Analysis of Phase IIA and IIB Experiments,” JAERI-M-89-154, Japan Atomic Energy Research Institute (Oct. 1989).
   Google Scholar
• M. Nakagawa and T. Mori, “Reactor Engineering Department Annual Report—April 1, 1988 to March 31, 1989,” JAERI-M-98-128, p. 129, Japan Atomic Energy Research Institute (Sep. 1989).
   Google Scholar
• M. Z. Youssef et al., “The Nuclear Analysis of an Annular Li20 Blanket System Surrounding an Artificially Simulated 14-MeV Line Source and Comparison of Calculations to Measurements,” Fusion Technol., 28, 320 (1995).
   Google Scholar
• Y. Oyama et al., “Concept and Characteristics of a Simulated Line Source for Annular Blanket Experiments Using an Accelerator-Based Deuterium-Tritium Neutron Source,” Fusion Technol., 28, 305 (1995).
   Web of Science ®Google Scholar
• M. Z. Youssef et al., “Analysis for the Simulation of a Line Source by a 14 MeV Moving Point Source and Impact on Blanket Characteristics: The USDOE/JAERI Collaborative Program on Fusion Neutronics,” Fusion Technol., 19, Part 2B, 1843 (1991).
   Google Scholar
• T. Nakamura et al., “A Line D-T Neutron Source Facility for Annular Blanket Experiment: Phase III of the JAERI/USDOE Collaborative Program on Fusion Neutronics,” Fusion Technol., 19, Part 2B, 1873 (1991).
   Google Scholar
• Y. Oyama et al., “Annular Blanket Experiment Using a Line DT Neutron Source: Phase IIIA of the JAERI/USDOE Collaborative Program on Fusion Neutronics,” Fusion Technol., 19, Part 2B, 1879 (1991).
   Google Scholar
• C. Konno et al., “Measurements of the Source Term for Annular Blanket Experiment with a Line Source: Phase IIIA of the JAERI/USDOE Collaborative Program on Fusion Neutronics,” Fusion Technol., 19, Part 2B, 1885 (1991).
   Google Scholar
• Y. Oyama et al., “Neutronics Integral Experiments of Lithium-Oxide Fusion Blanket with Heterogeneous Configuration Using Deuterium-Tritium Neutrons,” Fusion Technol., 28, 216 (1995).
   Google Scholar
• Y. Oyama et al., “Phase-IIC Experiments of the USDOE/JAERI Collaborative Program on Fusion Blanket Neutronics — Experiments and Analysis of the Heterogeneous Fusion Blankets — Volume I: Experimental Results,” JAERI-M-92-182, Japan Atomic Energy Research Institute (Dec. 1992);
   Google Scholar
  see also UCLA-FNT-63, UCLA-ENG-93-18, University of California, Los Angeles (Dec. 1992).
   Google Scholar
• M. Z. Youssef et al., “Phase-IIC Experiments of the USDOE/JAERI Collaborative Program on Fusion Blanket Neutronics — Experiments and Analysis of the Heterogeneous Fusion Blankets-Volume II: Analysis,” UCLA-FNT-64, UCLA-ENG-93-19, University of California, Los Angeles (Dec. 1992);
   Google Scholar
  see also M. NAKAGAWA et al., JAERI-M-92-183, Japan Atomic Energy Research Institute (Dec. 1992).
   Google Scholar
• M. Youssef et al., “Analysis for Heterogeneous Blankets and Comparison to Measurements: Phase IIC Experiments of the USDOE/JAERI Collaborative Program on Fusion Neutronics,” Fusion Technol., 19, Part 2B, 1891 (1991).
   Google Scholar
• Y. Oyama et al., “Measured Characteristics of Be Multi-Layered and Coolant Channel Blankets: Phase IIC Experiments of the JAERI/USDOE Collaborative Program on Fusion Neutronics,” Fusion Technol., 19, Part B, 1955 (1991).
   Google Scholar
• A. Kumar, Y. Watanabe, and M. Youssef, “Analysis of the Selection of Experimental Configuration for Heterogeneity and Be Multi-Layered Experiments of the USDOE/JAERI Collaborative Program on Blanket Neutronics,” Fusion Technol., 15, 1309 (1989).
   Web of Science ®Google Scholar
• LOS ALAMOS MONTE CARLO GROUP, “MCNPA General Monte Carlo Code for Neutron and Photon Transport,” Version 3A, LA-7396, Rev. 2, Los Alamos National Laboratory (1986).
   Google Scholar
• M. Nakagawa and T. Mori, “MORSE-DD, A Monte Carlo Code Using Multigroup Double Differential Form Cross-Sections,” JAERI-M84-126, Japan Atomic Energy Research Institute (July 1984).
   Google Scholar
• L. P. Ku and J. Kolibal, “RUFF-A Ray Tracing Program to Generate Uncollided Flux and First Collision Source Moments for DOT4, A User’s Manual,” EAD-R-16, Plasma Physics Laboratory, Princeton University (1985).
   Google Scholar
• W. A. Rhoades and R. L. Childs, “An Updated Version of the DOT 4 (Version 4.3) One-and-Two-Dimen-sional Neutron/Photon Transport Code,” ORNL-5851, Oak Ridge National Laboratory (Apr. 1982);
   Google Scholar
  see also CCC-429, Radiation Shielding Information Center (1982).
   Google Scholar
• “DOT 3.5: Two-Dimensional Discrete Ordinates Radiation Transport Code,” CCC-276, Radiation Shielding Information Center;
   Google Scholar
  see also W. A. Rhoades and F. R. Mynett, “The DOT III Two-Dimensional Discrete Ordinates Transport Code,” ORNL-TM-4280, Oak Ridge National Laboratory (Sep. 1973).
   Google Scholar
• R. A. MacFarlane, “TRANSX-CTR: A Code for Interfacing MATXS Cross-Section Libraries to Nuclear Transport Codes for Fusion Systems Analysis,” LA-9863-MS, Los Alamos National Laboratory (Feb. 1984).
   Google Scholar
• M. Z. Youssef et al., “The Prediction Capability for Tritium Production and Other Reaction Rates in Various Systems Configurations for a Series of the USDOE/JAERI Collaborative Fusion Blanket Experiments,” Fusion Eng. Des., 18, 407 (1991).
   Web of Science ®Google Scholar
• M. Z. Youssef et al., “Fusion Integral Experiments and Analysis and the Determination of Design Safety Factors — I: Methodology,” Fusion Technol., 28, 366 (1995).
   Web of Science ®Google Scholar
• Y. Ikeda and M. Z. Youssef, “Two-Dimensional Cross-Section Sensitivity and Uncertainty Analysis for Tritium Production Rate in Fusion-Oriented Integral Experiments,” Fusion Technol., 13, 616 (1988).
   Google Scholar
• P. M. Song, M. Z. Youssef, and M. A. Abdou, “New Approach and Computational Algorithm for Sensitivity/Uncertainty Analysis for SED and SAD with Application to Beryllium Integral Experiments,” Nucl. Sci. Eng., 113, 339 (1993).
   Web of Science ®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
• M. Z. Youssef and Y. Oyama, “Required Design Margins and Their Economic Impact in Fusion Reactors to Compensate for Nuclear Data Uncertainties — A Global Approach to Define Safety Factors Based on Integral Experiments,” Proc. Int. Conf. Nuclear Data for Science and Technology, Gatlinburg, Tennessee, May 9–13, 1994.
   Google Scholar
• Y. Oyama, K. Kosako, C. Konno, Y. Ikeda, F. Maekawa, and H. Maekawa, “Influence of Selection of Calculation Parameters in Discrete Ordinate Code DOT3.5 for Analysis of Fusion Blanket Integral Experiments in JAERI/USDOE Collaborative Program,” Fusion Eng. Des., 28, 636 (1995).
   Web of Science ®Google Scholar
• P. G. Young, “Evaluation of n+7Li Reactions Using Variance-Covariance Techniques,” Trans. Am Nucl. Soc., 39, 272 (1980).
   Google Scholar
• H. Maekawa, T. Nakamura, S. Azam, and P.-A. Haldy, “International Comparison on Measuring Techniques of Tritium Production Rate for Fusion Neutronics Experiments,” Interim NEACRP Report NEACRP-A-1021, Nuclear Energy Agency Committee on Reactor Physics (1989);
   Google Scholar
  see also Proc. Annual USDOE/JAERI Workshop on Fusion Blanket Neutronics and the Informal Int. Mtg. Fusion Neutronics, UCLA-FNT-60, ENG-93-15, University of California, Los Angeles (Aug. 1992).
   Google Scholar