[2F19-22] Core Design 1 (Na-cooled Reactor)

[2F20] Core design study on 750MWe JSFR with metal fuel

(1)Evaluation of fuel irradiation behavior

*Hirokazu Ohta¹, Kazuya Ohgama ², Takanari Ogata¹, Yoshihisa Ikusawa ², Shigeo Ohki ² (1. CRIEPI, 2. JAEA)

Keywords:Metal fuel, Fast reactor, Fuel design, Axial swelling, Bond sodium

For a 750MWe metal fuel core design, the metal fuel irradiation behaviors such as axial elongation and bond sodium migration were evaluated, and the effects of these behaviors on the core neutronics performance were analyzed. Based on an assumed irradiation condition, it was evaluated that axial elongation of fuel slug is ~ 8% and 80-90% of bond sodium migrates to upper plenum. Neutronics analysis revealed that such irradiation behavior causes reactivity change of a few dollars.