Characterization of High Temperature Creep Properties in Recrystallized 12Cr-ODS Ferritic Steel Claddings

Ukai, Shigeharu; Okuda, Takanari; Fujiwara, Masayuki; Kobayashi, Toshimi; Mizuta, Syunji; Nakashima, Hideharu

doi:10.1080/18811248.2002.9715271

Cited by 152 publications

(35 citation statements)

References 19 publications

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“…During the past few years, there is a growing interest in the development of non-swelling martensitic steels with the matrix strengthened by nano size yttrium oxides [9][10][11]. This approach is consistent with the approach for dispersion strengthening by fine particles.…”

Section: Oxide Dispersion Strengthened Steelssupporting

confidence: 57%

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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Section: Oxide Dispersion Strengthened Steelssupporting

confidence: 57%

Fast Reactor Technology for Energy Security: Challenges for Materials Development

Mannan

Mathew

Jayakumar

et al. 2013

JMMP

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“…Finer dispersoids with a higher number density have a stronger pinning effect on dislocations as suggested by the resultant hardness enhancement [19,55]. The pinning of grain boundaries, known as Zener pinning, has also been found to be inversely proportional to particle size.…”

Section: Discussionmentioning

confidence: 94%

Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: Coherent interfaces vs. incoherent interfaces

et al. 2016

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a b s t r a c tIn this study, the microstructure of a 12Cr ferritic-martensitic oxide-dispersion-strengthened (ODS) alloy is studied before and after Fe ion irradiation up to 200 peak displacements per atom (dpa). Irradiation temperature ranges from 325 to 625 C. Before irradiation, both coherent and incoherent dispersoids exist in the matrix. In response to irradiation, the mean sizes of dispersoids in both the ferrite and tempered martensite phases change to equilibrium values that increase with irradiation temperature. The evolution of dispersoids under irradiation is explained by a competition between athermalradiation-driven shrinkage and thermal-diffusion-driven growth, with interface coherency affecting the growth mechanism. However, each coherency type exhibits different evolution behavior under irradiation. Coherent dispersoids, regardless of their initial size, change toward an equilibrium size at each temperature tested. On the other hand, incoherent dispersoids are destroyed at lower test temperatures but survive while shrinking in size at higher temperatures. This difference in behavior can be explained by the lower interfacial energy of coherent dispersoids in comparison with incoherent dispersoids. This study sheds light on the roles of interface configurations in maintaining dispersoid integrity under irradiation.

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“…They also act as obstacles for dislocation migration at room temperature, as well as at high temperatures. A maximum hardening effect is reached with a minimum particle size which is equivalent to a maximum particle density …”

Section: Resultsmentioning

confidence: 99%

Bimodal Grain Size Distribution of Nanostructured Ferritic ODS Fe–Cr Alloys

2015

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Oxide dispersion strengthened Fe–Cr alloys produced by mechanical alloying and spark plasma sintering were found to form different heterogeneous hardness distribution and microstructures depending on the milling parameters. Microstructure investigations by means of electron‐diffraction techniques and atom probe tomography revealed the presence of large particle‐free zones in one material, which is, together with the inhomogeneous deformation at short milling times, considered the main reason for the formation of a heterogeneous microstructure. The inhomogeneous temperature distribution in the sample volume during the sintering process is also expected to contribute to the formation of a heterogeneous grain size distribution in the final material.

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Characterization of High Temperature Creep Properties in Recrystallized 12Cr-ODS Ferritic Steel Claddings

Cited by 152 publications

References 19 publications

Fast Reactor Technology for Energy Security: Challenges for Materials Development

Fast Reactor Technology for Energy Security: Challenges for Materials Development

Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: Coherent interfaces vs. incoherent interfaces

Bimodal Grain Size Distribution of Nanostructured Ferritic ODS Fe–Cr Alloys

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