Anish Ranjan
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Anish Ranjan has a total of 28 co-authors. Here are the top co-authors by number of shared publications:
- Haiming Wen
Department of Materials Science and Engineering, Missouri University of Science and Technology, Rolla, USA
2 shared publications - Aaron G. Penders
Idaho National Laboratory
1 shared publication - Akhilesh Goyal
Department of Mechanical Engineering Indian Institute of Technology Bombay Mumbai India
1 shared publication - Alexander Demblon
Texas A&M University
1 shared publication - Amit Singh
Department of Mechanical Engineering, IIT Bombay , Mumbai 400076
1 shared publication Andrew Hoffman
1 shared publication
Latest Publications
- Open Access
- 2 June 2026
- Published by SAGE Publications in International Materials Reviews
- Vol. 71 (5) , 472-504
Microstructure and properties of oxide dispersion-strengthened alloys
Oxide dispersion-strengthened (ODS) alloys are a critical class of structural materials for extreme environments, owing to their unique combination of high-temperature strength, thermal stability, and radiation tolerance, enabled by a very high density of nanoscale oxide dispersoids. These features make ODS alloys attractive for advanced nuclear systems, aerospace applications, and other harsh-service conditions where conventional alloys rapidly degrade. Despite decades of development, key challenges remain in understanding how nanoscale oxides interact with matrix microstructures, alloy chemistry, and irradiation-induced defects to control macroscopic performance. This review provides a focused, mechanism-based synthesis of the microstructural features that govern the properties of ODS alloys. Emphasis is placed on grain structure evolution, dispersoid size and distribution, matrix–particle interfaces, and the role of alloying elements in stabilizing oxide nanoparticles and controlling phase composition. Distinctions between ferritic, ferritic–martensitic, and austenitic ODS systems are discussed where relevant, highlighting how microstructural differences influence strengthening mechanisms, creep resistance, and thermal stability. The relationships between microstructure and properties are critically examined, including room- and elevated-temperature mechanical behavior, and long-term thermal stability. Particular attention is given to how dispersoid characteristics and grain-boundary structures influence deformation mechanisms, grain-boundary migration, and dispersoid stability during prolonged service. A dedicated section addresses radiation effects in ODS alloys, synthesizing insights from ion- and neutron-irradiation studies. Key phenomena such as defect sink behavior, He and hydrogen trapping, irradiation-induced dispersoid evolution, and changes in mechanical performance are discussed, supported by evidence from advanced characterization techniques, including TEM and atom probe tomography. Challenges associated with simulating neutron damage and predicting long-term irradiation performance are also highlighted. By integrating microstructure, mechanical properties, and irradiation response, this review provides a coherent framework to guide the design and assessment of next-generation ODS alloys for extreme environments.
- 2 June 2026
- Published by SAGE Publications in International Materials Reviews
- Vol. 71 (5) , 472-504
Open AccessMicrostructure and properties of oxide dispersion-strengthened alloys
Oxide dispersion-strengthened (ODS) alloys are a critical class of structural materials for extreme environments, owing to their unique combination of high-temperature strength, thermal stability, and radiation tolerance, enabled by a very high density of nanoscale oxide dispersoids. These features make ODS alloys attractive for advanced nuclear systems, aerospace applications, and other harsh-service conditions where conventional alloys rapidly degrade. Despite decades of development, key challenges remain in understanding how nanoscale oxides interact with matrix microstructures, alloy chemistry, and irradiation-induced defects to control macroscopic performance. This review provides a focused, mechanism-based synthesis of the microstructural features that govern the properties of ODS alloys. Emphasis is placed on grain structure evolution, dispersoid size and distribution, matrix–particle interfaces, and the role of alloying elements in stabilizing oxide nanoparticles and controlling phase composition. Distinctions between ferritic, ferritic–martensitic, and austenitic ODS systems are discussed where relevant, highlighting how microstructural differences influence strengthening mechanisms, creep resistance, and thermal stability. The relationships between microstructure and properties are critically examined, including room- and elevated-temperature mechanical behavior, and long-term thermal stability. Particular attention is given to how dispersoid characteristics and grain-boundary structures influence deformation mechanisms, grain-boundary migration, and dispersoid stability during prolonged service. A dedicated section addresses radiation effects in ODS alloys, synthesizing insights from ion- and neutron-irradiation studies. Key phenomena such as defect sink behavior, He and hydrogen trapping, irradiation-induced dispersoid evolution, and changes in mechanical performance are discussed, supported by evidence from advanced characterization techniques, including TEM and atom probe tomography. Challenges associated with simulating neutron damage and predicting long-term irradiation performance are also highlighted. By integrating microstructure, mechanical properties, and irradiation response, this review provides a coherent framework to guide the design and assessment of next-generation ODS alloys for extreme environments.
- 14 March 2026
- Published by Elsevier in Materialia
- Vol. 46
Atom probe tomography investigation of gas and solid fission product superlattice in neutron irradiated U-10 wt.% Mo fuel
- 14 March 2026
- Published by Elsevier in Materialia
- Vol. 46
Atom probe tomography investigation of gas and solid fission product superlattice in neutron irradiated U-10 wt.% Mo fuel
- 19 April 2024
- Published by Elsevier in Materials Science and Engineering: A
- Vol. 901
Microstructural effects and constitutive modelling of cyclic softening behaviour in Ti–6Al–4V titanium alloys
- 19 April 2024
- Published by Elsevier in Materials Science and Engineering: A
- Vol. 901
Microstructural effects and constitutive modelling of cyclic softening behaviour in Ti–6Al–4V titanium alloys