Sensitivity and uncertainty analyses of fission product nuclide inventories for passive gamma spectroscopy

References

• Sato S, Nauchi Y. Development of burnup confirmation technique for spent fuel-numerical simulation of measurement of burnup indicator by FP gamma-ray measurement. Japan: Central Research Institute of Electric Power Industry; 2017. p. L16002.
   Google Scholar
• McIsaac CV, Akers DW. TMI-2 core bore gamma ray spectroscopy measurements. Oak Ridge, TN: Technical Information Center; 1988. EGG-TMI-8058.
   Google Scholar
• Sagara H, Tomikawa H, Watahiki M, et al. Feasibility study of passive gamma spectrometry of molten core material from Fukushima Daiichi nuclear power station unit 1, 2, and 3 cores for special nuclear material accountancy – low-volatile FP and special nuclear material inventory analysis and fundamental characteristics of gamma-rays fuel debris. J Nucl Sci Technol. 2014;51:1–23.
   Web of Science ®Google Scholar
• Chiba G. Perturbation theory for nuclear fuel depletion calculations with predictor-corrector method. J Nucl Sci Technol. 2018;55(3):290–300.
   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):1–30.
   Web of Science ®Google Scholar
• Katakura J. JENDL FP decay data file 2011 and fission yields data file 2011. Japan: Japan Atomic Energy Agency; 2011. JAEA-Data/Code 2011-025.
   Google Scholar
• Katakura J, Minato F, Ohgama K. Revision of the JENDL FP fission yield data. EPJ Web Conf. 2016;111:08004.
   Google Scholar
• Brown DA, Chadwick MB, Capote R, et al. ENDF/B-VIII.0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data. Nucl Data Sheets. 2018;148:1–142.
   Google Scholar
• MacFarlane RE. NJOY99.0: code system for producing pointwise and multigroup neutron and photon cross sections from ENDF/B data. US: Los Alamos National Laboratory; 1999.
   Google Scholar
• Fiorito L, Stankovsky A, Van den Eynde G, et al. Generation of fission yield covariances to correct discrepancies in the nuclear data libraries. Ann Nucl Energy. 2016;88:12–23.
   Web of Science ®Google Scholar
• Devillers C. The importance of fission product nuclear data in reactor design and operation. IAEA Panel. 1977; Petten.
   Google Scholar
• Gandini A. A method of correlation of burnup measurements for physics prediction of fast power-reactor life. Nucl Sci Eng. 2011;48(1):1–7.
   Google Scholar
• Williams ML. Development of depletion perturbation theory for coupled neutron/nuclide fields. Nucl Sci Eng. 1979;70(1):20–36.
   Web of Science ®Google Scholar
• Chiba G, Endo T. Numerical benchmark problem of solid-moderated enriched-uranium-loaded core at Kyoto university critical assembly. J Nucl Sci Technol. 2019;57(2):187–195.
   Web of Science ®Google Scholar
• Okumura K, Kugo T, Kaneko K, et al. SRAC2006: a comprehensive neutronics calculation code system. Japan: Japan Atomic Energy Agency; 2007. JAEA-Data/Code 2007-004.
   Google Scholar
• Chiba G, Narabayashi T. Advanced Bondarenko method for resonance self-shielding calculations in deterministic reactor physics code system CBZ. Ann Nucl Energy. 2016;96:277–286.
   Web of Science ®Google Scholar
• Sugimura N, Yamamoto A. Evaluation of Dancoff factors in complicated geometry using the method of characteristics. J Nucl Sci Technol. 2006;43(10):1182–1187.
   Web of Science ®Google Scholar
• Kawamoto Y, Chiba G, Tsuji M, et al. Numerical solution of matrix exponential in burn-up equation using mini-max polynomial approximation. J Nucl Sci Technol. 2015;80:219–224.
   Google Scholar
• Chiba G, Ohoka Y, Yamamoto K, et al. Revisiting mini-max polynomial approximation method for nuclear fuel depletion calculations. Proceeding international conference on mathematics and computational methods applied to nuclear science and engineering; 2019 Aug 25-29; Portland (OR).
   Google Scholar
• Chiba G, Okumura S. Uncertainty quantification of neutron multiplication factors of light water reactor fuels during depletion. J Nucl Sci Technol. 2018;55(9):1043–1053.
   Web of Science ®Google Scholar
• Katakura J, Kataoka M, Suyama K, et al. A set of ORIGEN2 cross section libraries based on JENDL-3.3 library: ORLIBJ33. Japan: Japan Atomic Energy Research Institute; 2004. JAERI-Data/Code 2004-015.
   Google Scholar
• Burn-up credit criticality safety benchmark phase III-C. NEA/NSC/R/(2015)6. France: Organization for Economic Cooperation and Development, Nuclear Energy Agency; 2015.
   Google Scholar
• Koning AJ, Rochman D, Sublet J, et al. TENDL: complete nuclear data library for innovative nuclear science and technology. Nucl Data Sheets. 2019;155:1–55.
   Google Scholar