Monte Carlo calculation analysis of measurements of fission rate distributions in light-water-moderated cores loaded with mixed oxide and UO₂ fuels

References

• Remec I, Gehin JC, D’hondt P, et al. OECD/NEA KRITZ-2 UO2 and MOX benchmarks. Proc. PHYSOR 2002; 2002 Oct 7-10; Seoul, Korea.
   Google Scholar
• Snoj L, Gehin JC, Ravnik M, et al. KRITZ-2:19 experiment on regular H2O/fuel pin lattices with mixed oxide fuel at temperatures 21.1 and 235.9°C. OECD/NEA Nucl Sci.2019 Jul. (International Handbook of Evaluated Reactor Physics Benchmark Experiments, NEA/NSC/DOC(2006)01, KRITZ-LWR-RESR-001).
   Google Scholar
• Mondot J, Gauthier JC, Chaucheprat P, et al. EPICURE: an experimental programme devoted to the validation of the calculational schemes for plutonium recycling in PWR. Proc. PHYSOR 1990; 1990 Apr 23–27; Marseille, France.
   Google Scholar
• Chauvin JP, Cabrillat JC, Fougeras P, et al. Synthesis of an experimental programme devoted to the validation of the calculation scheme for the pressurized water reactor recycling MOX fuel. Proc. PHYSOR96; 1996 Sep 16–20; Mito, Japan.
   Google Scholar
• Minsart GL, D’Hondt PJ, Van der Meer K. VIP, an international programme of benchmark experiments for the study of MOX-fueled cores. Proceedings International Conference on Reactor Physics and Reactor Computation; 1994 Jan 23–26; Tel Aviv (Israel).
   Google Scholar
• Mori M, Kawamura M, Yamate K. CASMO-4/SIMULATE-3 benchmarking against high Plutonium content pressurized water reactor mixed-oxide fuel critical experiment. Nucl Sci Eng. 1995 Jan;12:41–51.
   Google Scholar
• Saji E, Shirayanagi H. Analyses of boiling water reactor mixed-oxide critical experiments with CASMO-4/ SIMULATE-3. Nucl Sci Eng. 1995;121:52–56.
   Web of Science ®Google Scholar
• Yamamoto T, Iwahashi D, Sakai T. Analysis of VIP-BWR reactor physics experiments on UO2 and MOX mockup fuel assemblies with CASMO5. J Nucl Sci Technol. 2019 Nov;56:1047–1058.
   Web of Science ®Google Scholar
• Cathalau S, Cabrillat JC, Chauvin JP, et al. MISTRAL: an experimental programme in the EOLE facility devoted to 100% MOX core physics. Proc. PHYSOR96; 1996 Sep 16–20; Mito, Japan.
   Google Scholar
• Yamamoto T, Iwata Y, Ueji M, et al. Analysis of MISTRAL experiments with JENDL-3.2. J Nucl Sci Technol. 2002 Aug:(Supplement 2);1061–1066. doi:https://doi.org/10.1080/00223131.2002.10875285.
   Google Scholar
• Yamamoto T, Iwata Y, Ueji M, et al. BASALA: advanced BWR MOX core physics experiments. Proc. PHYSOR2000; 2000 May 7–11; Pittsburgh, USA.
   Google Scholar
• Yamamoto T, Umano T, Kanda R, et al. Core physics experiments and their analysis of high moderation full MOX BWR. Proc. GENES4/ANP2003; 2003 Sep 15–19; Kyoto, Japan.
   Google Scholar
• Yamamoto T, Sakai T, Ando Y, et al. Neutronics analysis of full MOX BWR core physics simulation experiments FUBILA. J Nucl Sci Technol. 2011 Mar;48:398–420.
   Web of Science ®Google Scholar
• Yamamoto T, Sakai T, Ando Y, et al. Neutronics analysis of full MOX BWR core physics simulation experiments – FUBILA: part 2. J Nucl Sci Technol. 2012 Jan;49:103–120.
   Web of Science ®Google Scholar
• Murakami K, Tsuruta H, Suzaki T, et al. Critical experiment for power flattening in plutonium fuel lattice. Tokai-mura (Japan): Japan Atomic Energy Research Institute; 1982. (JAERI-M 9876). [Japanese].
   Google Scholar
• Tsuruta H, Matsuura S, Kobayashi I, et al. Critical experiments and analyses on 7 × 7 PuO₂-UO₂ lattices in light-water moderated UO₂ core. Tokai-mura (Japan): Japan Atomic Energy Research Institute; 1974. (JAERI 1234).
   Google Scholar
• Rahman M, Suzaki T, Mori T. Analysis study of two-region TCA critical experiments with PWR-type MOX fuel by using Monte Carlo code MVP. Tokai-mura (Japan): Japan Atomic Energy Research Institute; 2003. (JAERI-Research 2003-007).
   Google Scholar
• Mori T, Nakagawa M, Sasaki M. Vectorization of continuous energy Monte Carlo method for neutron transport calculation. J Nucl Sci Technol. 1992 Apr;29:325–336.
   Web of Science ®Google Scholar
• Nakagawa T, Shibata K, Chiba S, et al. Japanese evaluated nuclear data library version 3 revision-2: JENDL-3.2. J Nucl Sci Technol. 1995;32:1259–1271.
   Web of Science ®Google Scholar
• Shibata K, Kawano T, Nakagawa T, et al. Japanese evaluated nuclear data library version 3 revision-3: JENDL- 3.3. J Nucl Sci Technol. 2002;39:1125–1136.
   Web of Science ®Google Scholar
• Nagaya Y, Okumura K, Sakurai T, et al. MVP/GMVP version 3: general purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods. Tokai-mura (Japan): Japan Atomic Energy Agency; 2017. (JAEA-Data/Code 2016-018).
   Google Scholar
• Shibata K, Iwamoto O, Nakagawa T, et al. JENDL-4.0: a new library for nuclear science and engineering. J Nucl Sci Technol. 2011 Jan;48:1–30.
   Web of Science ®Google Scholar
• Yamamoto T, Miyoshi Y, Dean V. Critical arrays of mixed plutonium-uranium fuel rods with water-to-fuel volume ratios ranging from 2.4 to 5.6. OECD/NEA Nucl Sci. 2019 Jun. (International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC (95) 03/IV, MIX-COMP-THERM-004).
   Google Scholar
• Miyoshi Y, Arakawa T, Yamamoto T, et al. Critical arrays of low-enriched UO2 fuel rods with water-to-fuel volume ratios ranging from 1.5 to 3.0. OECD/NEA Nucl Sci, 2019 Jun. (International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC (95) 03/IV, LEU-COMP-THERM-006).
   Google Scholar
• Matsuura S, Kobayashi I, Turuta H, et al. Tokai-mura (Japan): Japan Atomic Energy Research Institute; 1969. (JAERI-memo 3438).
   Google Scholar
• Tsuruta H. Measurement of the ratio of fission product gamma activities from 239Pu and 235U fissions. J Nucl Sci Technol. 1973 Sep;10:550–565.
   Web of Science ®Google Scholar
• 2020 Aug. Available from: https://www.gabrian.com/6061-aluminum-properties/
   Google Scholar
• Jones FE, Harris GL. ITS-90 density of water formulation for volumetric standards calibration. J Res Natl Stand Technol. 1992 May–Jun;97:335–340.
   PubMed Web of Science ®Google Scholar
• Tsuruta H, Kobayashi I, Suzaki T, et al. Critical sizes of light-water moderated UO₂ and PuO₂-UO₂ lattices. Tokai-mura (Japan): Japan Atomic Energy Research Institute; 1978. (JAERI 1254).
   Google Scholar
• Compilation of the data book on light water reactor benchmark to develop the next version of JENDL - utilization of criticality data in ICSBEP and IRPhEP open databases. Tokai-mura (Japan): Japan Atomic Energy Agency; 2017 May. (JAEA-Data/Code 2017-006). [in Japanese].
   Google Scholar
• Yamamoto T. Critical analysis of light-water moderation UO2 and uranium-plutonium mixed oxide lattices by continuous-energy Monte Carlo calculation. J Nucl Sci Technol. 2021 Jan;58:845–855. DOI:https://doi.org/10.1080/00223131.2021.1879691.
   Web of Science ®Google Scholar