[2J05-09] Fuel Cladding Tube 1

[2J09] R&D of ODS ferritic steel cladding for maintaining fuel integrity at accident condition (3)

(5)Evaluation on tolerance to failure of existing ODS ferritic steel claddings at the accident conditions of fast reactors

*Tomoyuki Uwaba¹, Yasuhide Yano¹, Satoshi [e-mail]¹, Masayuki Naganuma¹, Takashi Tannno¹, Hiroshi Oka¹, Shoichi Kato¹, Takaji Kaito¹, Shigeharu Ukai², Akihiko Kimura³ (1. Japan Atomic Energy Agency, 2. Hokkaido University, 3. Kyoto University)

Keywords:oxide-dispersion-strengthened ferritic steel, fast reactors, fuel claddings, cumulative damage fractions

Tolerance of fast rector fuel elements to failure in the typical accident conditions was evaluated for the oxide-dispersion-strengthened (ODS) ferritic steel claddings that are candidate of the cladding material for advanced fast reactors. The evaluation was based on the cladding creep damage, which was quantified by the cumulative damage fractions (CDFs). It was shown that the CDFs of the ODS ferritic steel cladding were substantially lower than the breach limit of 1.0 in the loss of flow and transient over power conditions until a passive reactor shutdown system is actuated.