2017 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1 Nuclear Materials and the Irradiation Behavior

[2J05-09] Fuel Cladding Tube 1

Tue. Mar 28, 2017 2:45 PM - 4:10 PM Room J (16-305 Building No.16)

Chair: Kazunori Morishita (Kyoto Univ.)

3:45 PM - 4:00 PM

[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 yano.yasuhide@jaea.go.jp1, 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.