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Report No.

U-Pu-Zr metallic fuel core and fuel concept for SFR with a 550$$^{circ}$$C core outlet temperature

Naganuma, Masayuki  ; Ogata, Takanari*; Mizuno, Tomoyasu

In the FaCT project, a design study of the metallic fuel SFR has been executed as secondary candidate. The primary interest is to achieve a core outlet temperature of 550 $$^{circ}$$C. However, the metallic fuel has a drawback that the maximum temperature of the cladding inner surface is limited to 650 $$^{circ}$$C to avoid liquid phase formation. To overcome this problem, JAEA has developed and studied the advanced core concept with single Pu-enrichment and 2 radial regions of heavy metal density. In this paper, the core and fuel design study for the middle-scale SFR applying this core concept are discussed. In addition, for the practical application of the metallic fuel to the SFR with high outlet temperature, it is necessary to expand irradiation experience under the high cladding temperature condition. Therefore, JAEA and CRIEPI planned an irradiation test of the metallic fuel in Joyo as a collaborative program. In this paper, the outline and current status of the irradiation test are reported.



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