Narita, Takeshi; Ukai, Shigeharu 
; Kaito, Takeji ; Otsuka, Satoshi 
; Matsuda, Yasushi*
The oxide dispersion strengthened (ODS) ferritic-martensitic steels are being developing for application as advanced fast reactor cladding and fusion blanket materials, in order to allow increased operation temperature. Water corrosion test of ODS ferritic-martensitic steels was conducted under a controlled alkali water environment to evaluate the water corrosion behavior, comparing to conventional 17 mass% Cr austenitic stainless steel (PNC316) and 11 mass% Cr ferritic-martensitic stainless steel (PNC-FMS). It was showed that 9Cr-ODS martensitic steel and 12Cr-ODS ferritic steel have superior water corrosion resistance, and comparable to that of PNC316 and PNC-FMS at 333K for 1,000h under varying pH of 8.4, 10, 12.
Language |
: | English |
|---|---|---|
Journal |
: | |
Volume |
: | 45 |
Number |
: | 2 |
Pages |
: | p.99 - 102 |
Publication Year/Month |
: | 2008/02 |
Meeting title |
: | 12th International Conference on Fusion Reactor Materials (ICFRM-12) |
Held date |
: | 2005/12 |
Location (city) |
: | Santa Barbara |
Location (country) |
: | U.S.A. |
Paper URL |
: |
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Keywords |
: | no keyword |
Accesses |
: |
- Accesses |
|---|---|---|
InCites™ |
: |
Percentile:34.98 Category:Nuclear Science & Technology |
Altmetrics |
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