TY - GEN
T1 - Super ODS steels R&D for cladding of highly efficient nuclear plants
AU - Kimura, Akihiko
AU - Cho, Hangsik
AU - Toda, Naoki
AU - Kasada, Ryuta
AU - Kishimoto, Hirotatsu
AU - Iwata, Noriyuki
AU - Ukai, Shigeharu
AU - Ohtsuka, Satoshi
AU - Fujiwara, Masayuki
PY - 2008
Y1 - 2008
N2 - Cladding materials development is essential to realize highly efficient and high-burnup operation over 100GWd/t of so called Generation IV nuclear energy system. Oxide dispersion strengthening (ODS) ferritic/ martensitic steels, which contain 9-12%Cr, show rather high resistance to neutron irradiation embrittlement and high strength at elevated temperatures. However, their corrosion resistance is not good enough in supercritical pressurized water and in lead at high temperatures. In order to improve corrosion resistance of the ODS steels in such environment, high-Cr ODS steels have been developed at Kyoto University. An increase in Cr content resulted in a drastic improvement of corrosion resistance in SCW and in lead, while it was expected to cause an enhancement of aging embrittlement as well as Irradiation embrittlement. Anisotropy in tensile properties is another issue. In order to overwhelm these issues, surveillance tests of the material performance have been performed for high Cr-ODS steels produced by new processing technologies. It is demonstrated that high-Cr ODS steels have a high potential as fuel cladding materials for SCWR and LFR with high efficiency and high burnup.
AB - Cladding materials development is essential to realize highly efficient and high-burnup operation over 100GWd/t of so called Generation IV nuclear energy system. Oxide dispersion strengthening (ODS) ferritic/ martensitic steels, which contain 9-12%Cr, show rather high resistance to neutron irradiation embrittlement and high strength at elevated temperatures. However, their corrosion resistance is not good enough in supercritical pressurized water and in lead at high temperatures. In order to improve corrosion resistance of the ODS steels in such environment, high-Cr ODS steels have been developed at Kyoto University. An increase in Cr content resulted in a drastic improvement of corrosion resistance in SCW and in lead, while it was expected to cause an enhancement of aging embrittlement as well as Irradiation embrittlement. Anisotropy in tensile properties is another issue. In order to overwhelm these issues, surveillance tests of the material performance have been performed for high Cr-ODS steels produced by new processing technologies. It is demonstrated that high-Cr ODS steels have a high potential as fuel cladding materials for SCWR and LFR with high efficiency and high burnup.
KW - F0200
KW - F0800
KW - M0500
KW - O0200
KW - P0200
KW - S1000
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M3 - Conference contribution
AN - SCOPUS:52249096998
SN - 9781604238716
T3 - Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"
SP - 2148
EP - 2154
BT - Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"
T2 - Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"
Y2 - 13 May 2007 through 18 May 2007
ER -