Behavior under Neutron Irradiation of the 15-15Ti and EM10 Steels Used as Standard Materials of the Phénix Fuel Subassembly

Seran, Jean-Louis; Levy, V.; Gilbon, D.; Maillard, A; Fissolo, A.; Touron, H.; Cauvin, R.; Chalony, A.; Boulbin, E. Le

doi:10.1520/stp17941s

Cited by 31 publications

(19 citation statements)

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“…12) This Ms point is reasonably interpreted as indicating the presence of interstitial carbon in the steel, and only small influence of oxide particles. In contrast, the minimal cooling rate to obtain martensite phase is ranged in a few hundred K/h for 9Cr-ODS martensitic steel, whereas conventional ferriticmartensitic steels take around 20 K/h, depending on the prior austenite grain size; finer grains display higher critical cooling rate.…”

Section: Continuous Cooling Transformationmentioning

confidence: 80%

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Development of 9Cr-ODS Martensitic Steel Claddings for Fuel Pins by means of Ferrite to Austenite Phase Transformation

Ukai¹,

Mizuta²,

Fujiwara

et al. 2002

Journal of Nuclear Science and Technology

147

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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 austenitic PNC316 at higher temperature and extended time to rupture. The strength improvement is mainly attributed to titanium addition in ODS martensitic steels through its reduction of Y 2 O 3 particle size and shortening inter-particles spacing. The behavior of oxide particle size reduction is associated with stoichiometry between Y 2 O 3 and TiO 2 .

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Section: Continuous Cooling Transformationmentioning

confidence: 80%

“…The claddings produced is tested to determine their high temperature mechanical properties by means of ring tensile 12) and internally pressurized creep rupture tests. These form of testing were selected to prove their resistance against the dominant direction of loading in an actual fuel pin, i.e.…”

Section: Evaluation Testsmentioning

confidence: 99%

Development of 9Cr-ODS Martensitic Steel Claddings for Fuel Pins by means of Ferrite to Austenite Phase Transformation

Ukai¹,

Mizuta²,

Fujiwara

et al. 2002

Journal of Nuclear Science and Technology

147

View full text Add to dashboard Cite

show abstract

“…The produced claddings are tested to determine their high temperature mechanical properties by means of ring tensile 10) and internally pressurized creep rupture tests. These tests were selected to prove their resistance against the dominant direction of loading in an actual fuel pin, i.e.…”

Section: Test Of Mechanical Properties and Microstructural Observationmentioning

confidence: 99%

Production and Properties of Nano-scale Oxide Dispersion Strengthened (ODS) 9Cr Martensitic Steel Claddings

Ukai¹,

Kaito²,

Ohtsuka³

et al. 2003

ISIJ International

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“…Unlike titanium, the swelling temperature does not vary too much with nickel content under ions irradiation [35]. Ni is known to increase the incubation dose for swelling [11,25,35,41,42]. In our experiment, Ni decreases the cavities mean size but increases their density.…”

Section: L50m3mentioning

confidence: 46%

“…Swelling under irradiation depends on various microstructural parameters such as the dislocation density [4][5][6][7], precipitates [7][8][9][10] and the chemical elements in solid solution [8,[11][12][13][14][15]. Besides, the role of each of them can be direct or indirect [16].…”

Section: Introductionmentioning

confidence: 99%

Influence of the austenitic stainless steel microstructure on the void swelling under ion irradiation

Rouxel

Bisor

Carlan

et al. 2016

EPJ Nuclear Sci. Technol.

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Abstract. To understand the role of different metallurgical parameters on the void formation mechanisms, various austenitic stainless steels were elaborated and irradiated with heavy ions. Two alloys, in several metallurgical conditions (15Cr/15Ni-Ti and 15Cr/25Ni-Ti), were irradiated in the JANNUS-Saclay facility at 600°C with 2 MeV Fe 2+ ions up to 150 dpa. Resulting microstructures were observed by Transmission Electron Microscopy (TEM). Different effects on void swelling are highlighted. Only the pre-aged samples, which were consequently solute and especially titanium depleted, show cavities. The nickel-enriched matrix shows more voids with a smaller size. Finally, the presence of nano-precipitates combined with a dense dislocation network decreases strongly the number of cavities.

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Behavior under Neutron Irradiation of the 15-15Ti and EM10 Steels Used as Standard Materials of the Phénix Fuel Subassembly

Cited by 31 publications

References 0 publications

Development of 9Cr-ODS Martensitic Steel Claddings for Fuel Pins by means of Ferrite to Austenite Phase Transformation

Development of 9Cr-ODS Martensitic Steel Claddings for Fuel Pins by means of Ferrite to Austenite Phase Transformation

Production and Properties of Nano-scale Oxide Dispersion Strengthened (ODS) 9Cr Martensitic Steel Claddings

Influence of the austenitic stainless steel microstructure on the void swelling under ion irradiation

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