Improvement of compatibility of advanced ferritic steels with super critical pressurized water toward a higher thermally efficient water-cooled blanket system
- 1. Graduate School of Energy Science, Kyoto University, Gokasho, Uji, Kyoto (Japan)
- 2. Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto (Japan)
- 3. Japan Nuclear Cycle Development Institute, Tokai (Japan)
- 4. Kobelco Ltd., Takatsukadai, Nishi-ku, Kobe (Japan)
Description
Various oxide dispersion strengthened (ODS) steels which have high Cr concentrations with and without Al addition were made by mechanical alloying method. Corrosion measurement was done in the closed system of super critical pressurized water (SCPW) at 783 K with the pressure of 25 MPa. In order to evaluate the mechanical properties and the effect of thermal aging, a miniaturized Charpy V notch (MCVN) test and tensile test were performed before and after aging at 773 K up to 1000 h. The susceptibility to stress corrosion cracking (SCC) of high Cr-ODS steels was evaluated by slow strain rate test (SSRT). The SSRT was performed in a simulated boiling water reactor (BWR) condition with high temperature oxygenated (8-10 ppm) water at 561 K and at a pressure of 7.8 MPa. Strain rates were ranging from 1 x 10-4 to 3 x 10-7 s-1. The high Cr-ODS steels showed a better resistance to corrosion than SUS316L stainless steel in SCPW. The 14Cr and 16Cr-ODS steel did not suffer from aging embrittlement at 773 K for 1000 h. The ODS steels showed no susceptibility to SCC at strain rates from 1 x 10-4 to 3 x 10-7 s-1
Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2005.09.056;
- PII
- S0920-3796(05)00630-7;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 81
- Journal Issue
- 8-14
- Journal Page Range
- p. 1071-1076
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 7. international symposium on fusion nuclear technology
- Acronym
- ISFNT-7
- Dates
- 22-27 May 2005
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37109439
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; BWR TYPE REACTORS; COMPATIBILITY; CRACKING; EMBRITTLEMENT; FERRITIC STEELS; MECHANICAL PROPERTIES; OXIDES; STAINLESS STEELS; STRAIN RATE; STRESS CORROSION; THERMONUCLEAR REACTOR MATERIALS; WATER
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHALCOGENIDES; CHEMICAL REACTIONS; CORROSION; DECOMPOSITION; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; OXYGEN COMPOUNDS; POWER REACTORS; PYROLYSIS; REACTORS; STEELS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.