On a fast reactor cycle scheme that incorporates a thoria-based minor actinide-containing cermet fuel

Progress in Nuclear Energy

Volumn 50, Issue 2-6, 2008, Pages 212-218

  Osaka, Masahiko ^a   Takano, Sho ^b   Yamane, Yoshihiro ^b   Misawa, Tsuyoshi ^c  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b NAGOYA UNIVERSITY   (Japan)

^c KYOTO UNIVERSITY   (Japan)

Author keywords

Americium; Cermet; Core characteristics; Molybdenum; Reprocessing; Thorium

Indexed keywords

ACTINIDES; CERMETS; INCINERATION; SOLID SOLUTIONS;

CERMET FUEL; CORE CHARACTERISTICS; INCINERATION DEVICES;

FAST REACTORS;

EID: 39549122202     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2007.11.002     Document Type: Article

References (25)

1. Amamoto I., Sato K., and Terai T. Behavior of FPs and TRU in a fluoride volatility process. Recent Advances in Actinide Science (2006), RSC Publishing, Cambridge, UK 578 pp.
2. 2. J. Nucl. Mater. 250 (1997) 1
3. 2±X. J. Nucl. Mater. 118 (1983) 220
4. Donnet, L., Jorion, F., Drin, N., et al., 2005. The FUTURIX-FTA experiment in PHENIX: status of fuel fabrication. In: Proceedings of the International Conference GLOBAL2005, paper No. 258. Tsukuba, Japan, 9-13 October.
5. Fernandez A., Konings R.J.M., and Somers J. Design and fabrication of specific ceramic-metallic fuels and targets. J. Nucl. Mater. 319 (2003) 44
6. Fowler, T.B., Vondy, D.R., Cunningham, G.W., 1969. Nuclear reactor core analysis code: citation. Oak Ridge National Laboratory Report ORNL-TM-2496.
7. Hazama, T., Chiba, G., Numata, K., et al., 2002. Development of the unified cross section set ADJ2000R for fast reactor analysis. Japan Nuclear Cycle Development Institute Report JNC TN9400 2002-064.
8. Hirosawa, T., Tanaka, K., Morimoto, K., et al., 2004. Development of fabrication technique for MOX pellet containing americium by the remote control (VII) - outline of improved apparatus and melting temperature measurement of Am-containing MOX fuel. In: Proceedings Fall Mtg. Atom. Ene. Soc. Jpn, Kyoto, Japan, 15-17 September, 573 pp. (in Japanese).
9. International Atomic Energy Agency, 2005. Thorium fuel cycle - potential benefits and challenges. IAEA-TECDOC-1450.
10. Kleykamp H. Selection of materials as diluents for burning of plutonium fuels in nuclear reactors. J. Nucl. Mater. 275 (1999) 1
11. Lung M., and Gremm O. Perspective of the thorium fuel cycle. Nucl. Eng. Des. 180 (1998) 133
12. Matzke H.J., Rondinella V.V., and Wiss T. Materials research on inert matrices: a screening study. J. Nucl. Mater. 274 (1999) 47
13. 2-X. J. Alloys Compd. 213-214 (1994) 456
14. Naganuma, M., Ogawa, T., Takaki, N., et al., 2003. Design study on core and fuel properties of sodium cooled fast reactor (mixed oxide fuel core) - results in JFY2003. Japan Nuclear Cycle Development Institute Report JNC TN9400-039 (in Japanese).
15. Nakagawa, M., Tsuchihashi, K., 1984. SLAROM: a code for cell homogenization calculation of fast reactor. Japan Atomic Energy Research Institute Report JAERI 1294.
16. Namekawa, T., Kawaguchi, K., Koike, K., et al., 2005. Conceptual design study and evaluation of advanced fuel fabrication systems in the feasibility study on commercialized FR fuel cycle in Japan. In: Proceedings of the International Conference GLOBAL2005, paper No. 424, Tsukuba, Japan, 9-13 October.
17. Nazare S., Ondracek G., and Thummler F. Die technologie von cermets. High Temperatures - High Pressures 3 (1971) 615 (in German)
18. Oigawa, H., Yokoo, T., Nishihara, K., et al., 2005. Parametric survey on possible impact of partitioning and transmutation of high-level radioactive waste. In: Proceedings of the International Conference GLOBAL2005, paper No. 266. Tsukuba, Japan, 9-13 October.
19. 2-X solid solutions. J. Alloys Compd. 397 (2005) 110
20. Osaka M., Koi M., Takano S., et al. A novel concept for americium-containing target for use in fast reactors. J. Nucl. Sci. Technol. 43 (2006) 367
21. 2-X on phase relation. Recent Advances in Actinide Science (2006), RSC Publishing, Cambridge, UK 406 pp.
22. Sagayama, Y., 2005. Feasibility study on commercialized fast reactor cycle systems (1) current status of the Phase-II study. In: Proceedings of the International Conference on GLOBAL2005, paper No. 380. Tsukuba, Japan, 9-13 October.
23. Sato, K., Koma, Y., Nakabayashi, H., et al., 2005. Conceptual design study and evaluation of advanced reprocessing plants in the feasibility study on commercialized FR cycle systems in Japan. In: Proceedings of the International Conference GLOBAL2005, paper No. 502. Tsukuba, Japan, 9-13 October.
24. Schmidt H.E., Sari C., and Richter K. The thermal conductivity of oxides of uranium, neptunium and americium at elevated temperatures. J. Less-Comm. Met. 121 (1986) 621
25. Wallenius J. Neutronic aspects of inert matrix fuels for application in ADS. J. Nucl. Mater. 320 (2003) 142