References
- K. TSUJIMOTO et al., “Neutronics Design for Lead-Bismuth Cooled Accelerator-Driven System for Transmutation of Minor Actinide,” J. Nucl. Sci. Technol., 41, 21 (2004); https://doi.org/10.1080/18811248.2004.9715454.
- K. TSUJIMOTO et al., “Research and Development Program on Accelerator Driven Subcritical System in JAEA,” J. Nucl. Sci. Technol., 44, 483 (2007); https://doi.org/10.1080/18811248.2007.9711312.
- K. NISHIHARA et al., “Neutronics Design of Accelerator-Driven System for Power Flattening and Beam Current Reduction,” J. Nucl. Sci. Technol., 45, 812 (2008); https://doi.org/10.1080/18811248.2008.9711482.
- “A Technology Roadmap for Generation IV Nuclear Energy Systems,” U.S. Department of Energy Nuclear Energy Research Advisory Committee and Generation IV International Forum (2002); https://www.gen4.org/gif/jcms/c_40481/technology-roadmap.
- “Technology Roadmap Update for Generation IV Nuclear Energy Systems,” Organisation for Economic Co-operation and Development Nuclear Energy Agency for the Generation IV International Forum (2013); https://www.gen-4.org/gif/jcms/c_60729/technology-roadmap-update-2013.
- K. SHIBATA et al., “JENDL-4.0: A New Library for Nuclear Science and Engineering,” J. Nucl. Sci. Technol., 48, 1 (2011); https://doi.org/10.1080/18811248.2011.9711675.
- H. IWAMOTO et al., “Sensitivity and Uncertainty Analysis for an Accelerator-Driven System with JENDL-4.0,” J. Nucl. Sci. Technol., 50, 856 (2012); https://doi.org/10.1080/00223131.2013.811954.
- A. TSIBOULIA et al., “Validation of Neutron Data for Pb and Bi Using Critical Experiments,” J. Nucl. Sci. Technol., 39, Suppl. 2, 1010 (2002); https://doi.org/10.1080/00223131.2002.10875272.
- C. H. PYEON et al., “Validation of Pb Nuclear Data by Monte Carlo Analyses of Sample Reactivity Experiments at Kyoto University Critical Assembly,” J. Nucl. Sci. Technol., 53, 602 (2016); https://doi.org/10.1080/00223131.2015.1068716.
- C. H. PYEON et al., “Experimental Analyses of Bismuth Sample Reactivity Worth at Kyoto University Critical Assembly,” J. Nucl. Sci. Technol., 55, 1324 (2018); https://doi.org/10.1080/00223131.2018.1506368.
- M. FUKUSHIMA et al., “Lead Void Reactivity Worth in Two Critical Assembly Cores with Differing Uranium Enrichments,” Nucl. Sci. Eng., 189, 93 (2018); https://doi.org/10.1080/00295639.2017.1373520.
- M. FUKUSHIMA et al., “Benchmark Models for Criticalities of FCA-IX Assemblies with Systematically Changed Neutron Spectra,” J. Nucl. Sci. Technol., 53, 406 (2016); https://doi.org/10.1080/00223131.2015.1054911.
- M. FUKUSHIMA et al., “Analyses with Latest Major Nuclear Data Libraries of the Fission Rate Ratios for Several TRU Nuclides in the FCA-IX Experiments,” J. Nucl. Sci. Technol., 54, 795 (2017); https://doi.org/10.1080/00223131.2017.1299644.
- R. LELL et al., “ZPPR-21 Phase A: A Cylindrical Assembly of Pu Metal Reflected by Graphite,” in “International Handbook of Evaluated Criticality Safety Benchmark Experiments,” PU-MET-FAST-033, NEA/NSC/DOC/(95)03/I, Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Nuclear Science Committee.
- T. GOORLEY et al., “Initial MCNP6 Release Overview,” Nucl. Technol., 180, 298 (2012); https://doi.org/10.13182/NT11-135.
- J. GODA et al., “Improvements in Void Reactivity Worth Measurements Using a Load Cell as Pressure Sensor,” Proc. Int. Conf. Nuclear Criticality Safety (ICNC 2019), Paris, France, September 15–20, 2019.
- D. A. BROWN 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, 148, 1 (2018); https://doi.org/10.1016/j.nds.2018.02.001.
- R. MOSTELLER et al., “The Initial Set of Zeus Experiments: Intermediate-Spectrum Critical Assemblies with a Graphite-HEU Core Surrounded by a Copper Reflector,” HEU-MET-INTER-006, NEA/NSC/DOC/(95)03/II, in “International Handbook of Evaluated Criticality Safety Benchmark Experiments,” Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Nuclear Science Committee.
- D. HAYES, “Zeus: Fast-Spectrum Critical Assemblies with an Iron-HEU Core Surrounded by a Copper Reflector,” HEU-MET-FAST-072, NEA/NSC/DOC/(95)03/II, in “International Handbook of Evaluated Criticality Safety Benchmark Experiments,” Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Nuclear Science Committee.
- R. MOSTELLER, “The Unmoderated Zeus Experiment: A Cylindrical HEU Core Surrounded by a Copper Reflector,” HEU-MET-FAST-073, NEA/NSC/DOC/(95)03/II, in “International Handbook of Evaluated Criticality Safety Benchmark Experiments,” Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Nuclear Science Committee.
- M. B. CHADWICK et al., “ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data,” Nucl. Data Sheets, 112, 2887 (2011); https://doi.org/10.1016/j.nds.2011.11.002.
- K. SHIBATA et al., “Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3,” J. Nucl. Sci. Technol., 39, 1125 (2002); https://doi.org/10.1080/18811248.2002.9715303.
- “International Criticality Safety Benchmark Evaluation Project (ICSBEP),” Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Nuclear Science Committee; https://www.oecd-nea.org/science/wpncs/icsbep/ (current as of Aug. 20, 2019)
- “International Reactor Physics Experiment Evaluation (IRPhE) Project,” Organisation for Economic Co-operation and Development, Nuclear Energy Agency, Nuclear Science Committee; https://www.oecd-nea.org/science/wprs/irphe/ (current as of Aug. 20, 2019)