References
- 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.
- Young JA, Koppel JU. Phonon spectrum of graphite. J Chem Phys. 1965;42(1):357–364.
- 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.
- Fujita I, Eto M, Ohsaki H, et al. Evaluation of oxidation characteristics of fine-grained graphites (IG-110 and IG-430) for very high temperature reactor - changes in density distribution and compressive strength caused by air-oxidation-. Oarai-machi (Japan): japan Atomic Energy Agency; 2013, (JAEA-Research 2013-004) [in Japanese].
- Jin Y, Yoshida K, Li Z, et al. Investigation of kinetic recovery process in low dose neutron-irradiated nuclear graphite by thermal annealing. J Nucl Sci Technol. 2019;56(6):533–540. .
- Ishiyama S, Eto M, Oku T. Effect of oxidation on fracture toughness of nuclear graphites. Tanso. 1992;1992(152):67–73. in Japanese.
- Nojiri N, Yamashita K, Fujimoto N, et al. Evaluation of accuracy of Monte Carlo code MVP with VHTRC experiments. Multiplication factor at criticality, burnable poison worth and void worth. Tokai-mura (Japan): Japan Atomic Energy Research Inst.;1997 (No. JAERI-TECH–97-060). [in Japanese]
- Gould CR, Hawari AI, Sharapov EI. Re-analysis of recent neutron diffusion and transmission measurements in nuclear graphite. Nucl Sci Eng. 2010;165(2):200–209.
- Kitamura Y, Eguchi Y. Uncertainty analysis of temperature effect on reactivity in very high temperature reactor critical assembly and establishment of biases for benchmark models. Nucl Sci Eng. 2014;178(3):401–413.
- Conlin JL, Ji W, Lee JC, et al. Pseudo material construct for coupled neutronic-thermal-hydraulic analysis of VHTGR. Trans Am Nucl Soc. 2006;92:225–227.
- Tada K, Nagaya Y, Kunieda S, et al. Development and verification of a new nuclear data processing system FRENDY. J Nucl Sci Technol. 2017;54(7):806–817. .
- Hawari AI, Gillete VH. Inelastic thermal neutron scattering cross sections for reactor-grade graphite. Nucl Data Sheets. 2014;118:176–178.
- Yamane T, Yasuda H, Akino F, et al. Measurement of overall temperature coefficient of reactivity of VHTRC-1 core by pulsed neutron method. J Nucl Sci Technol. 1990;27(2):26–36. .
- 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; 2016, (JAEA-Data/Code 2016-018).
- Okumura K, Nagaya Y Production of neutron cross section library based on JENDL-4.0 to continuous-energy Monte Carlo code MVP and its application to criticality analysis of benchmark problems in the ICSBEP handbook. Tokai-mura (Japan): Japan Atomic Energy Agency; 2011, (JAEA-Data/Code 2011-010) [in Japanese].