Uncertainty quantification of criticality in solid-moderated and -reflected cores at Kyoto University Critical Assembly

References

• Misawa T, Unesaki H, Pyeon CH. Nuclear reactor physics experiments. Kyoto, Japan: Kyoto University Press; 2010.
   Google Scholar
• Pyeon CH, Hirano Y, Misawa T, et al. Preliminary experiments for accelerator driven subcritical reactor with pulsed neutron generator in Kyoto University Critical Assembly. J Nucl Sci Technol. 2007;44:1368–1378.
   Web of Science ®Google Scholar
• Pyeon CH, Hervault M, Misawa T, et al. Static and kinetic experiments on accelerator-driven system with 14 MeV neutrons in Kyoto University Critical Assembly. J Nucl Sci Technol. 2008;45:1171–1182.
   Web of Science ®Google Scholar
• Pyeon CH, Shiga H, Misawa T, et al. Reaction rate analyses for an accelerator-driven system with 14 MeV neutrons in Kyoto University Critical Assembly. J Nucl Sci Technol. 2009;46:965–972.
   Web of Science ®Google Scholar
• Lim JY, Pyeon CH, Yagi T, et al. Subcritical multiplication parameters of the accelerator-driven system with 100 MeV protons at the Kyoto University Critical Assembly. Sci Technol Nucl Install. 2012; 395878:9.
   Web of Science ®Google Scholar
• Pyeon CH, Azuma T, Takemoto Y, et al. Experimental analyses of external neutron source generated by 100 MeV protons at the Kyoto University Critical Assembly. Nucl Eng Technol. 2013;45:81–88.
   Web of Science ®Google Scholar
• Pyeon CH, Nakano H, Yamanaka M, et al. Neutron characteristics of solid targets in accelerator-driven system with 100 MeV protons at Kyoto University Critical Assembly. Nucl Technol. 2015;192:181–190.
   Web of Science ®Google Scholar
• Lagrange JB, Planche T, Yamakawa E, et al. Straight scaling FFAG beam line. Nucl Instrum Methods A. 2013;691:55–63.
   Web of Science ®Google Scholar
• Yamakawa E, Uesugi T, Lagrange JB, et al. Serpentine acceleration in zero-chromatic FFAG accelerators. Nucl Instrum Methods A. 2013;716:46–53.
   Web of Science ®Google Scholar
• Pyeon CH, Yamanaka M, Endo T, et al. Experimental benchmarks on kinetic parameters in accelerator-driven system with 100 MeV protons at Kyoto University Critical Assembly. Ann Nucl Energy. 2017;105:346–354.
   Web of Science ®Google Scholar
• Pyeon CH, Fujimoto A, Sugawara T, et al. Validation of Pb nuclear data by Monte Carlo analyses of sample reactivity experiments at Kyoto University Critical Assembly. J Nucl Sci Technol. 2016;53:602–612.
   Web of Science ®Google Scholar
• Pyeon CH, Fujimoto A, Sugawara T, et al. Sensitivity and uncertainty analyses of lead sample reactivity experiments at Kyoto University Critical Assembly. Nucl Sci Eng. 2017;185:460–472.
   Web of Science ®Google Scholar
• Tsujimoto K, Sasa T, Nishihara K, et al. Neutronics design for lead-bismuth cooled accelerator-driven system for transmutation of minor actinide. J Nucl Sci Technol. 2004;41:21–36.
   Web of Science ®Google Scholar
• Abderrahim HA, D'hondt P. MYRRHA: a European experimental ADS for R&D applications status at mid-2005 and prospective towards implementation. J Nucl Sci Technol. 2007;44:491–498.
   Web of Science ®Google Scholar
• Fukushima M, Kitamura Y, Kugo T, et al. Benchmark models for criticalities of FCA-IX assemblies with systematically changed neutron spectra. J Nucl Sci Technol. 2016;53:406–424.
   Web of Science ®Google Scholar
• Shibata K, Iwamoto O, Nakagawa T, et al. JENDL-4.0: a new library for nuclear science and technology. J Nucl Sci Technol. 2011;48:1–30.
   Web of Science ®Google Scholar
• Goorley JT, James MR, Booth TE, et al. Initial MCNP6 release overview – MCNP6 version 1.0. 2013. ( LA-UR-13-22934).
   Google Scholar
• Chadwick MB, Oblozinsky P, Herman M, et al. ENDF/V-II.0: next generation evaluated nuclear data library for nuclear science and technology. Nucl Data Sheet. 2006;107:2931–3060.
   Web of Science ®Google Scholar
• Okumura K, Kugo T, Kaneko K, et al. SRAC2006: a comprehensive neutronic calculation code system. 2007. ( JAERI-Data/Code 2007-004).
   Google Scholar
• Yokoyama K, Hazama T, Numata K, et al. Development of comprehensive and versatile framework for reactor analysis, MARBLE. Ann Nucl Energy. 2014;66:51–60.
   Web of Science ®Google Scholar
• Fowler TB, Vondy DR. Nuclear reactor core analysis code: citation. 1969. ( ORNL-TM-2496, Rev. 2).
   Google Scholar
• Hara A, Takeda T, Kikuchi Y. SAGEP: two-dimensional sensitivity analysis code based on generalized perturbation theory. 1984. ( JAERI-M 84-027).
   Google Scholar
• Hazama T, Chiba G, Sugino K, et al. Development of fine and ultra-fine group cell calculation code SLAROM-UF for fast reactor analysis. J Nucl Sci Technol. 2006;43:908–918.
   Web of Science ®Google Scholar
• Usachev LN. Perturbation theory for the breeding ratio and for other number ratios pertaining to various reactor processes. J Nucl Energy. 1964;18:571–583.
   Google Scholar
• Gandini A. A generalized perturbation method for bi-linear functionals of the real and adjoint neutron fluxes. J Nucl Energy. 1967;21:755–765.
   Web of Science ®Google Scholar
• Cecchini GP, Salvatores M. Advances in the generalized perturbation theory. Nucl Sci Eng. 1971;46:304–309.
   Web of Science ®Google Scholar
• Kobayashi K. Reactor physics. Tokyo, Japan: Corona Publishing Co. Ltd.; 1996. Japanese.
   Google Scholar
• Cacuci DG. On the neutron kinetics and control of accelerator-driven systems. Nucl Sci Eng. 2004;148:55–66.
   Web of Science ®Google Scholar
• Broadhead BL, Rearden BT, Hopper CM, et al. Sensitivity- and uncertainty-based criticality safety validation techniques. Nucl Sci Eng. 2004;146:340–366.
   Web of Science ®Google Scholar
• Dragt JB, Dekker JM, Grupperlaar H, et al. Methods of adjustment and error evaluation of neutron capture cross sections; application to fission product nuclides. Nucl Sci Eng. 1977;62:117–129.
   Web of Science ®Google Scholar
• Cacuci DG, Inoescu-bujor M. Best-estimate model calibration and prediction through experimental data assimilation: I. mathematical framework. Nucl Sci Eng. 2010;165:18–44.
   Web of Science ®Google Scholar