Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor

＊Masayoshi UNO

Presentation information

Oral Presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 401-1. Basic Properties

[3G10-13] Measure for failure of containment vessel

Mon. Mar 28, 2016 2:45 PM - 3:55 PM Room G (Lecture Rooms B B203)

Chair: Tsuyoshi Nishi (Ibaraki University)

3:30 PM - 3:45 PM

[3G13] Development of Estimation Technology for Availability of Measure for Failure of Containment vessel in Sodium Cooled Fast Reactor

(10)Thermal properties of Sodium Uranate

＊Masayoshi UNO¹, Keisuke YOKOYAMA¹, Murakami YUKIHIRO¹ (1.University of Fukui)

Keywords:fuel, sodium cooled fast reactor, severe accident, sodium uranate

Thermal expansion, heat capacity and thermal conductivity from room temperature to about 1200 degree C for Na₂U₂O₇, which is relatively stable at high temperature among sodium uranates will be reported.