Fuel pin irradiation test at up to 5 at % burnup in BOR-60 for oxide-dispersion-strengthened ferritic steel claddings

Journal of Nuclear Science and Technology

Volumn 46, Issue 6, 2009, Pages 529-533

  Kaito, Takeji ^a   Ukai, Shigeharu ^a,c   Povstyanko, Alexander V ^b   Efimov, Vladimir N ^b  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b RESEARCH INSTITUTE OF ATOMIC REACTORS   (Russian Federation)

^c HOKKAIDO UNIVERSITY   (Japan)

Author keywords

BOR 60; Cladding material; Fast reactor material; FCCI; Fuel pin; Irradiation; MOX fuel; O M ratio; ODS

Indexed keywords

BOR-60; CLADDING MATERIAL; FAST REACTOR MATERIAL; FCCI; MOX FUEL; O/M RATIO; ODS;

CHEMICAL REACTIONS; CHROMIUM; CLADDING (COATING); CORROSION; DISPERSIONS; FAST REACTORS; FERRITE; FERRITIC STEEL; FISSION PRODUCTS; IRRADIATION; OXYGEN; STEEL METALLOGRAPHY; TRANSURANIUM ELEMENTS; URANIUM;

FUELS;

EID: 67650723559     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.3327/jnst.46.529     Document Type: Article

References (10)

1. H. Niwa, K. Aoto, M. Morishita, "Current status and perspective of advanced loop type fast reactor in fast reactor cycle technology development project," Proc. GLOBAL 2007, Boise, Idaho, Sep. 9-13, 2007, 62 (2007), [CD-ROM].
2. S. Ukai, S. Mizuta, M. Fujiwara, T. Okuda, T. Kobayashi, "Development of 9Cr-ODS martensitic steel claddings for fuel pins by means of ferrite to austenite phase transformation," J. Nucl. Sci. Technol., 39[7], 778 (2002).
3. S. Ukai, T. Okuda, M. Fujiwara, T. Kobayashi, S. Mizuta, H. Nakashima, "Characterization of high temperature creep properties in recrystallized 12Cr-ODS ferritic steel claddings," J. Nucl. Sci. Technol., 39[8], 872 (2002).
4. S. Ukai, M. Fujiwara, "Perspective of ODS alloys application in nuclear environments," J. Nucl. Mater., 307-311, 749 (2002).
5. S. Ukai, T. Kaito, S. Ohtsuka, T. Narita, M. Fujiwara, T. Kobayashi, "Production and properties of nano-scale oxide dispersion strengthened (ODS) 9Cr martensitic steel claddings," ISIJ International, 43[12], 2038 (2003).
6. S. Ukai, T. Kaito, M. Seki, A. A. Mayorship O. V. Shishalov, "Oxide dispersion strengthened (ODS) fuel pin fabrication for BOR-60 irradiation test," J. Nucl. Sci. Technol., 42[1], 109 (2005).
7. M. Seki, H. Hirako, S. Kono, Y. Kihara, T. Kaito, S. Ukai, "Pressurized resistance welding technology development in 9Cr-ODS martensitic steels," J. Nucl. Mater., 329-333, 1534 (2004).
8. D. R. Olander, "Fundamental Aspects of Nuclear Reactor Fuel Elements," TID-26711-P1, USDOE (1976).
9. H. Kashihara, S. Shikakura, Y. Yokouchi, I. Shibahara, H. Matsushima, K. Yamamoto, "Dimensional stability of FBR fuel pins with modified type 316 stainless steel cladding at high burn-up," Proc. Int. Conf. on Fast Reactor Core and Fuel Structural Behaviour, Inverness, UK, Jun. 4-6, 1990,243 (1990).
10. R. Herbig, K. Rudolph, B. Lindau, O. V. Skiba, A. A. Maershin, "Vibrocompacted fuel for the liquid metal reactor BOR-60," J. Nucl. Mater., 204, 93 (1993).