Title of article :
Ferritic steel-blanket systems integration R&D—Compatibility assessment
Author/Authors :
Kimura، نويسنده , , A. and Kasada، نويسنده , , R. and Kohyama، نويسنده , , A. and Konishi، نويسنده , , S. and Enoeda، نويسنده , , M. and Akiba، نويسنده , , M. and Jitsukawa، نويسنده , , S. and Ukai، نويسنده , , S. and Terai، نويسنده , , T. and Sagara، نويسنده , , A.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2006
Pages :
8
From page :
909
To page :
916
Abstract :
The reduced activation ferritic steel (RAFS) has been selected as structural material for a variety of blanket systems for ITER test blanket modules (TBM). In the evaluation of integrated performance of ferritic steels as structural components of blanket systems, there are unique issues as well as common issues for each blanket system. One of the unique issues for each system is the compatibility of ferritic steels with the coolant materials. The corrosion rate of ferritic steels in hot water, super critical pressurized water (SCPW), humid air, Pb–17Li, lithium and Flibe at various temperatures is reviewed in this work. Efforts to improve corrosion resistance have been made, taking the alloy design into account. A dispersion of yttria was effective to improve corrosion resistance of a RAFS. The compatibilities of RAFSs with hot water, Pb–17Li, lithium and Flibe are considered to be good enough for the TBM applications. The liquid metal embrittlement (LME) is considered to be a critical issue for the utilization of RAFSs for the lithium systems. Several issues towards DEMO and beyond are shown from the compatibility point of view.
Keywords :
Test blanket modules , Liquid metals , water , Compatibility , salt , Ferritic steels
Journal title :
Fusion Engineering and Design
Serial Year :
2006
Journal title :
Fusion Engineering and Design
Record number :
2352934
Link To Document :
بازگشت