2017 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 401-2 Nuclear Fuel and the Irradiation Behavior

[1I13-17] characteristics of fuel cladding

Mon. Mar 27, 2017 4:25 PM - 5:50 PM Room I (16-304 Building No.16)

Chair: Ken Kurosaki (Osaka Univ.)

5:25 PM - 5:40 PM

[1I17] The Relationship between the Circumferential Strain and the Bending Strength after Quench of the Fuel Cladding Ballooned during a LOCA

*Takanori YUMURA1, Masaki AMAYA1 (1. JAEA)

Keywords:Fuel cladding, Loss-of-coolant accident, Circumferential Strain, Bending Strength, four-point bending test

LOCA時の温度履歴を模擬した条件下で膨れ破裂及び酸化させた未照射被覆管を用いて4点曲げ試験を実施した。その結果、膨れ量の増加に伴い曲げ強度が低下する傾向が見られた。これは被覆管の機械強度を左右するprior-β相厚さが膨れ量の増加に伴い減少する影響と考えられる。