High Burnup Fuel Cladding Materials R and D for Advanced Nuclear Systems

Akihiko Kimura, Han Sik Cho, Naoki Toda, Ryuta Kasada, Kentaro Yutani, Hirotatsu Kishimoto, Noriyuki Iwata, Shigeharu Ukai, Masayuki Fujiwara

研究成果: Article査読

97 被引用数 (Scopus)

抄録

Cladding materials development is crucial to realize highly efficient and high-burnup operation over 100GWd/t of so called Generation IV nuclear energy systems, such as supercritical-water-cooled reactor (SCWR) and lead-cooled fast reactor (LFR). 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 resistanceis not good enough in SCW and in lead at high temperatures. Inorder 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.

本文言語English
ページ(範囲)323-328
ページ数6
ジャーナルjournal of nuclear science and technology
44
3
DOI
出版ステータスPublished - 2007 3月
外部発表はい

ASJC Scopus subject areas

  • 核物理学および高エネルギー物理学
  • 原子力エネルギーおよび原子力工学

フィンガープリント

「High Burnup Fuel Cladding Materials R and D for Advanced Nuclear Systems」の研究トピックを掘り下げます。これらがまとまってユニークなフィンガープリントを構成します。

引用スタイル