References
- Onuki K, Inagaki Y, Hino R, et al. Research and development on nuclear hydrogen production using HTGR at JAERI. Prog Nucl Energy. 2005;47(1–4):496–503. .
- Saito S, Tanaka T, Sudo Y, et al. Design of High Temperature Engineering Test Reactor (HTTR). JAERI. 1994;1332:45–82.
- Yamashita K, Maruyama S, Murata I, et al. Optimization of power distribution to achieve outlet gas-coolant temperature of 950 °C for HTTR. J Nucl Sci Technol. 1992;29(5):472–481. .
- Goto M, Seki Y, Inaba Y, et al. Conceptual design of small-sized HTGR system (2). Nuclear design. JAEA-Technology. 2012;2012(17): 1–38. [ in Japanese]
- Lindeme TB, Pearson RL. Kernel migration for HTGR fuels from the system Th‐U‐Pu‐C‐O‐N. J Am Ceram Soc. 1977;60(1–2):5–14.
- Ueta S, Aihara J, Yasuda A, et al. Fabrication of uniform ZrC coating layer for the coated fuel particle of the very high temperature reactor. J Nucl Mater. 2008;376(2):146–151. .
- Fukuda K, Ogawa T, Hayashi K, et al. Research and development of HTTR coated particle fuel. J Nucl Sci Technol. 1991;28(6):570–581. .
- Gulden TD. Carbon Thermal Diffusion in the UC2‐C System. J Am Ceram Soc. 1972;55(1):14–18.
- Wagner-Loffler M. Amoeba behavior of UO2 coated particle fuel. Nucl Technol. 1977;35(2):392–402.
- Aihara J, Goto M, Inaba Y, et al. Preliminary evaluation of integrity of coated fuel particles under normal operation in core of small-sized HTGR system HTR50S at 1st. step of Phase I. JAEA Technol. 2012;2014(9):1–29. [ in Japanese].
- Hayashi K, Sawa K, Shinozawa S, et al. Assessment of fuel integrity of the High Temperature Engineering Test Reactor (HTTR) and its permissible design limit. JAERI-M. 1989;89(162):1–77. [ in Japanese]
- Duderstadt JJ, Hamilton LJ. Nuclear reactor analysis. New York: John Wiley& Sons; 1976.
- Inaba Y, Nishihara T. Development of fuel temperature calculation code for HTGRs. Ann Nucl Energy. 2017;101:383–389.
- Maruyama S, Ymashita K, Fujimoto N, et al. Determination of hot spot factors for calculation of the maximum fuel temperatures in the core thermal and hydraulic design of HTTR. JAERI-M. 1988;88(250):1–88. [ in Japanese]
- Okuno H, Sato S, Sakai T, et al. Nuclear criticality safety evaluation of a mixture of MOX, UO2 and additive in the most conservative concentration distribution. J Nucl Sci Technol. 2008;45(11):1108–1115.