2017 Fall Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 302-1 Advanced Reactor System

[1J05-08] Pu-burning Gas-cooled Reactor

Wed. Sep 13, 2017 2:45 PM - 3:55 PM Room J (C309 - C Block)

Chair:Masatoshi Kuroda (Kumamoto Univ.)

3:15 PM - 3:30 PM

[1J07] Development of Security and Safety Fuel for Pu-burner HTGR

(16)Experimental Study on the Transient Oxidation of Nuclear Graphite under Air Ingress Conditions

*Wataru SAGAWA1, Yang Wu1, Penghui Chai2, Masahiro Kondo1, Koji Okamoto1 (1. The University of Tokyo, 2. The University of Tokyo(currently working at JAEA))

Keywords:HTGR, Graphite, Severe accident, Air ingress accident, Transient temperature change

Transient temperature change of graphite, which is the main material of HTGR, during air ingress accident was experimentally investigated at differenet oxygen density to evaluate the safety of HTGR.