TY - JOUR
T1 - Ferritic steel-blanket systems integration R&D - Compatibility assessment
AU - Kimura, A.
AU - Kasada, R.
AU - Kohyama, A.
AU - Konishi, S.
AU - Enoeda, M.
AU - Akiba, M.
AU - Jitsukawa, S.
AU - Ukai, S.
AU - Terai, T.
AU - Sagara, A.
PY - 2006/2
Y1 - 2006/2
N2 - 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.
AB - 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.
KW - Compatibility
KW - Ferritic steels
KW - Liquid metals
KW - Salt
KW - Test blanket modules
KW - Water
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U2 - 10.1016/j.fusengdes.2005.09.018
DO - 10.1016/j.fusengdes.2005.09.018
M3 - Conference article
AN - SCOPUS:32544440957
SN - 0920-3796
VL - 81
SP - 909
EP - 916
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
IS - 8-14 PART B
T2 - Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part B
Y2 - 22 May 2005 through 27 May 2005
ER -