2002
DOI: 10.1080/18811248.2002.9715260
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Development of 9Cr-ODS Martensitic Steel Claddings for Fuel Pins by means of Ferrite to Austenite Phase Transformation

Abstract: For use as fuel cladding of liquid metal fast reactors, Fe-0.12C-9Cr-2W ODS martensitic steel claddings were developed by cold-rolling under the softened ferrite phase induced by slow cooling from austenite phase, subsequently by ferrite to austenite phase transformation to break up substantially elongated grains produced by cold-rolling at the final heat-treatment. The produced claddings showed noticeable improvement in tensile and creep rupture strength that are considerably superior to PNC-FMS and even aust… Show more

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Cited by 147 publications
(34 citation statements)
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“…The temperatures obtained (around 850°C for starting point Ac 1 and 900°C for finishing point Ac 3 ) are similar to phase transformation temperatures of conventional martensitic steel and of other 9Cr-ODS materials [14][15][16].…”
Section: Phase Transformationsupporting
confidence: 48%
“…The temperatures obtained (around 850°C for starting point Ac 1 and 900°C for finishing point Ac 3 ) are similar to phase transformation temperatures of conventional martensitic steel and of other 9Cr-ODS materials [14][15][16].…”
Section: Phase Transformationsupporting
confidence: 48%
“…Oxide dispersion strengthened (ODS) steels have been identified as a promising candidate structural material for Generation IV and fusion reactors because of their superior high-temperature mechanical properties and improved radiation resistance compared to conventional ferritic/martensitic steels [1][2][3]. These properties are achieved by introducing stable oxide dispersoids into the ferritic matrix which act as pinning sites for dislocations, sinks for radiation-induced point defects and limit grain growth [4][5][6][7][8].…”
Section: Introductionmentioning
confidence: 99%
“…Owing to the exceptional strength, creep and fatigue properties in addition to thermomechanical stability and irradiation resistance, oxide-dispersion-strengthened (ODS) alloys were initially designed for nuclear reactor applications [1][2][3][4][5][6][7][8][9][10][11][12][13]. These outstanding mechanical properties, capable of a wide range of operating temperatures, offer superior performance in a number of environmental conditions.…”
Section: Introductionmentioning
confidence: 99%