2011 Fall Meeting
Session ID : E22
Conference information
Development of ODS ferritic steel claddings for fast reactor fuels
(2)Material irradiation test in JOYO
*SHINICHIRO YAMASHITA, YASUHIDE YANO, RYUICHIRO OGAWA, MASAKI INOUE, TSUNEMITSU YOSHITAKE
Author information
Keywords:
Oxide Dispersion Strengthened (ODS) Steel Cladding Tube,
Core Materials of Fast Reactor,
Verification on Reliability of Material Performance Under Irradiation,
Post Irradiation Examination,
Neutron Irradiation Behavior
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