Japan's future HTR - The GTHTR300

Nuclear Engineering and Design

Volumn 233, Issue 1-3, 2004, Pages 309-327

  Kunitomi, Kazuhiko ^a   Katanishi, Shoji ^a   Takada, Shoji ^a   Takizuka, Takakazu ^a   Yan, Xing ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; COSTS; ELECTRIC POWER GENERATION; ELECTRICITY; GAS COOLED REACTORS; GAS TURBINES; RESEARCH AND DEVELOPMENT MANAGEMENT;

DEPLOYMENT; ELECTRICITY COSTS; JAPAN; PLANT DESIGN;

HIGH TEMPERATURE REACTORS;

EID: 10644277260     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2004.08.026     Document Type: Conference Paper

References (20)

1. Clappison, G.A., Mysen, A., 2002. The first stage of licensing of PBMR in South Africa and safety issues. In: Proceedings of Workshop on Advanced Nuclear Reactor Safety Issues and Research Needs, pp. 209-221.
2. Fowler, T.B., Vondy, D.R., Cunningham, 1971. Nuclear Reactor Core Analysis Code CITATION, ORNL-TM-2496, Oak Ridge National Laboratory.
3. Kadak, A., et al., 2001. Pebble Bed Modular Reactor, ANS Winter meeting Reno, Nevada, November 11-15.
4. Kosugiyama, S., Takei, M., et al., 2003. Maintenance methods and procedures for the power conversion system of the gas turbine high temperature reactor 300 (GTHTR300) (in Japanese).
5. Kunitomi, K., et al., 1998. Conceptual design of a 50MW severe-accident-free HTR and the related test program of the HTTR. Nucl. Technol. 123, 245.
6. Latherop, K.D., Brinkley, F.W., 1973. TWOTRAN-2: An Interfaced Exportable Version of the TWOTRAN Code for Two-Dimensional Transport, LA-4848-MS, Los Alamos National Laboratory.
7. Lohnert, G.H., 1990. Technical design features and essential safety-related properties of the HTR-module. Nucl. Eng. Design 121, 259-275.
8. Maruyama, S., Fujimoto, N., Sudo, Y., Murakami, T., Fujii, S., 1994. Evaluation of core thermal and hydraulic characteristics of HTTR. Nucl. Eng. Design 152, 183-196.
9. Mori, T., Nakagawa, M., 1994. MVP/GMVP:GeneraI purpose Monte Carlo codes for neutron and photon transport calculations based on continuous energy and multigroup methods, JAERI-Data/Code 94-007, Japan Atomic Energy Research Institute (in Japanese).
10. Nicholls, D.R., 1996. Utility Requirements for HTGRs, Proceedings of the Technical Committee Mtg. High Temperature Gas Cooled Reactor Technology Development, Commercializing the HTGR, Johannesburg, Republic of South Africa, November 13-15, International Atomic Energy Agency.
11. Sawa, K., Shiozawa, S., Minato, K., et al., 1996. Development of a coated fuel particle failure model under high burnup irradiation. J. Nucl. Sci. Technol. 33, 712.
12. Sawa, K., Sumita, J., Watanabe, T., 1999. Fuel failure and fission gas release analysis code in HTGR, JAERI-M 90-048, Jpn. At. Energy Res. Inst. (in Japanese).
13. Shindo, R., Yamashita, K., and Murata, I., 1990. One-Dimensional Fuel Cell Burnup Analysis Code for High Temperature Gas-cooled Reactors (HTGRs), JAERI-M 90-048, Jpn. At. Energy Res. Inst. (in Japanese).
14. Simon, W. A. and Shenoy, A. S., 1997. International cooperation in developing the GT-MHR evolution and program status, In: Proceedings of an IAEA Technical Committee Meeting, Petten, The Netherlands, 10-12 November, pp. 67-80.
15. Takizuka, T., Takada, S., et al., 2004. R&D for the GTHTR300, to appear in this issue.
16. Van Heek, A.I., 1994. Status of the HTR-Programme in the Netherlands, Proc. Workshop of the Role of Modular HTRs in Netherlands, Petten, The Netherlands, November 28-30, p. 83.
17. Xu, Y., Zuo, K., 1999. Studies on High temperature Research Reactor in China, In: Proceedings of the Sixth Asian Symposium on Research Reactors, Oarai Research Establishment, Japan, March 29-31, pp. 9-16.
18. Yamashita, K., Shindo, Y., Murata, I., Maruyama, S., Fujimoto, N., Takeda, T., 1996. Nuclear design of the high-temperature engineering test reactor (HTTR). Nucl. Sci. Eng. 122, 212-228.
19. Yan, X., Shiozawa, S., et al., 2000. Design innovations in GTHTR300 gas turbine high temperature reactor, ICONE-8016, Proceedings of the Eighth International Conference on Nuclear Engineering, Baltimore, MD, USA, April 2-6.
20. Yan, X., Kunitomi, K., et al., 2003. GTHTR300 design and development. Nucl. Eng. Design 222, 247-264.