Effect of titanium on the creep deformation behaviour of 14Cr–15Ni–Ti stainless steel

Latha, S.; Mathew, M.D.; Parameswaran, P.; Nandagopal, M.; Mannan, S.L.

doi:10.1016/j.jnucmat.2010.12.240

Cited by 26 publications

(3 citation statements)

References 14 publications

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“…The material under investigation is a candidate in-core material for future commercial fast reactors. IFAC-1 is a modified version of alloy D9 and has been developed indigenously by optimizing the phosphorus and silicon content to achieve high burn up [29]. During manufacturing of components for in-core application, this steel has to undergo various thermomechanical treatments [23].…”

Section: Materials and Experimentsmentioning

confidence: 99%

Constitutive flow behavior of IFAC-1 austenitic stainless steel depicting strain saturation over a wide range of strain rates and temperatures

Samantaray¹,

Patel²,

Borah³

et al. 2014

Materials & Design (1980-2015)

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Section: Materials and Experimentsmentioning

confidence: 99%

Constitutive flow behavior of IFAC-1 austenitic stainless steel depicting strain saturation over a wide range of strain rates and temperatures

Samantaray¹,

Patel²,

Borah³

et al. 2014

Materials & Design (1980-2015)

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“…% and silicon of 0.75 wt. % (Fig.5) [6]. The alloys have been irradiated using 5 MeV nickel ions on (30 appm helium pre-implanted) to a peak damage of 100 dpa at a damage rate of 7 × 10 -3 dpa/s at various irradiation temperatures between 700 and 970 K. The void swelling, measured by step height, was found to be lower for the sample containing higher amount of phosphorous with the peak swelling at 2.5 % (Fig.6).…”

Section: Austenitic Stainless Steelsmentioning

confidence: 99%

Fast Reactor Technology for Energy Security: Challenges for Materials Development

Mannan

Mathew

Jayakumar

et al. 2013

JMMP

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Fuel cycle cost of sodium cooled fast reactors is strongly dependent on the performance of core structural materials, i.e., clad and wrapper materials of the fuel subassembly, which are subjected to intense neutron irradiation during service, that leads to unique materials problems like void swelling, irradiation creep and helium embrittlement. In order to increase the burnup of the fuel and thereby reduce the fuel cycle cost, it is necessary to employ materials which have high resistance to void swelling as well as better high temperature mechanical properties. The Indian fast reactor program began with the commissioning of the 40 MW t Fast Breeder Test Reactors (FBTR). The core structural material of FBTR is 20% cold worked 316 austenitic stainless steel (SS). For the 1250 MW t Prototype Fast Breeder Reactor which is nearing completion of construction, 20% cold-worked alloy D9 (15Cr-15Ni-Ti) has been selected as the clad and wrapper material. The target burnup is 100 GWd/t. Advanced austenitic stainless steel called as IFAC-1 SS and oxide dispersion strengthened martensitic steels have been developed as future materials for achieving higher burnup. Type 316 SS and its modified versions are used as the major high temperature structural materials for out-of-core permanent components. Ferritic-martensitic steels are selected for steam generator applications. This paper reviews the unique problems in fast reactors and illustrates the global progress in developing advanced structural materials for fast reactors in the context of the Indian nuclear programme.

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“…In order to design an alloy with enhanced resistance to both void swelling and creep, a series of laboratory heats were produced by varying the compositions of Ti, Si and P in alloy D9. The void swelling resistance, creep properties, tensile properties, weldability and microstructural stability of these heats have been systematically investigated and the composition has been optimised leading to the development of the new alloy called as IFAC-1 SS [2,3]. This paper presents the details of the development of this alloy, its properties and the associated joining technology.…”

Section: Introductionmentioning

confidence: 99%

Development of IFAC-1 SS: An Advanced Austenitic Stainless Steel for Cladding and Wrapper Tube Applications in Sodium-Cooled Fast Reactors

Mathew

Gopal

Murugan

et al. 2013

AMR

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Fuel cycle cost of sodium cooled fast reactors (SFRs) is strongly dependent on the in-reactor performance of core structural materials, i.e., cladding and wrapper tube materials of the fuel subassembly, which are subjected to intense neutron irradiation during service, leading to unique materials problems like void swelling, irradiation creep and helium embrittlement. In order to increase the burnup of the fuel and thereby reduce the fuel cycle cost, it is necessary to employ materials which have high resistance to void swelling as well as better high temperature mechanical properties. The Indian fast reactor program began with the commissioning of the 40 MWtFast Breeder Test Reactor (FBTR). The core structural material of FBTR is 20% cold worked 316 austenitic stainless steel (SS). For the 5000 MetPrototype Fast Breeder Reactor (PFBR) which is in an advanced stage of construction at Kalpakkam, 20% cold-worked alloy D9 (14Cr-15Ni-Ti SS) has been selected as the cladding and wrapper tube material for the initial core. The target burnup of the fuel is 100 GWd/t. Advanced austenitic stainless steel and oxide dispersion strengthened steels are being developed for achieving fuel burnup higher than 100 GWd/t. An advanced alloy D9 containing controlled amounts of titanium, silicon and phosphorous has been developed. This alloy named as IFAC-1 (Indian Fast Reactor advanced Clad-1) SS is aimed at thermal creep properties comparable to that of alloy D9, and superior void swelling resistance upto a target burn-up of about 150 GWd/t. The nominal chemical composition of IFAC-1 SS is 14Cr-15Ni-.25Ti-.75Si-.04P. The chemical composition has been optimized after extensive evaluation of the tensile, creep and microstructural stability of fifteen laboratory heats with different amounts of titanium, silicon and phosphorous. Void swelling behavior was studied using ion irradiation. IFAC-1 SS contains higher levels of low melting eutectic phase forming elements such as phosphorous, and so is susceptible to solidification cracking. Extensive pulsed TIG welding trials have been carried out on IFAC-1 SS/316LN SS weld joints with varied weld parameters to find out the feasibility of obtaining solidification crack-free welds and the optimum welding parameters have been established. This paper gives an overview of the development of this advanced core structural material for SFRs.

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Effect of titanium on the creep deformation behaviour of 14Cr–15Ni–Ti stainless steel

Cited by 26 publications

References 14 publications

Constitutive flow behavior of IFAC-1 austenitic stainless steel depicting strain saturation over a wide range of strain rates and temperatures

Constitutive flow behavior of IFAC-1 austenitic stainless steel depicting strain saturation over a wide range of strain rates and temperatures

Fast Reactor Technology for Energy Security: Challenges for Materials Development

Development of IFAC-1 SS: An Advanced Austenitic Stainless Steel for Cladding and Wrapper Tube Applications in Sodium-Cooled Fast Reactors

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