M. Kolluri
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View article: Transmission electron microscopy study of the synergistic effects of Mn, Ni and Si on neutron irradiated RPV model steels
Transmission electron microscopy study of the synergistic effects of Mn, Ni and Si on neutron irradiated RPV model steels Open
View article: Assessment of Ni and Mn effect on the irradiation hardening behavior of VVER-1000 model steels exposed to high fluences in the high flux reactor
Assessment of Ni and Mn effect on the irradiation hardening behavior of VVER-1000 model steels exposed to high fluences in the high flux reactor Open
View article: The LYRA-10 Experiment: Irradiation of Light Water Reactor Pressure Vessel Steels with Systematic Variations in Ni, Mn, and Si Contents to Assess Long-Term Operation–Enhanced Embrittlement
The LYRA-10 Experiment: Irradiation of Light Water Reactor Pressure Vessel Steels with Systematic Variations in Ni, Mn, and Si Contents to Assess Long-Term Operation–Enhanced Embrittlement Open
View article: Magic-RR project overview: objectives, methodology and expected results
Magic-RR project overview: objectives, methodology and expected results Open
Most research reactors (RRs) in Europe are over 60 years old, and there are only limited efforts underway (e.g., PALLAS and JHR projects) to partially replace this aging infrastructure. Continued safe operation (CSO) of these reactors is c…
View article: Transmission Electron Microscopy Study of the Synergistic Effects of Mn, Ni And Si on Neutron Irradiated Rpv Model Steels
Transmission Electron Microscopy Study of the Synergistic Effects of Mn, Ni And Si on Neutron Irradiated Rpv Model Steels Open
View article: Assessment of Ni and Mn Effect on the Irradiation Hardening Behavior of Vver-1000 Model Steels Exposed to High Fluences in the High Flux Reactor
Assessment of Ni and Mn Effect on the Irradiation Hardening Behavior of Vver-1000 Model Steels Exposed to High Fluences in the High Flux Reactor Open
View article: Master curve reference temperature behavior of steels with varying Ni/Mn content and subjected to a fluence of 11·1019 neutron/cm2
Master curve reference temperature behavior of steels with varying Ni/Mn content and subjected to a fluence of 11·1019 neutron/cm2 Open
View article: Investigation of Irradiation Hardening and Effectiveness of Post-Irradiation Annealing on the Recovery of Tensile Properties of VVER-1000 Realistic Welds Irradiated in the LYRA-10 Experiment
Investigation of Irradiation Hardening and Effectiveness of Post-Irradiation Annealing on the Recovery of Tensile Properties of VVER-1000 Realistic Welds Irradiated in the LYRA-10 Experiment Open
Assessing the embrittlement and hardening of reactor pressure vessel steels is critical for the extension of the service lifetime of nuclear power plants. This paper summarises the tensile test results on the irradiation behaviour of reali…
View article: Present Status of the Fractesus Project: Round Robin on Unirradiated Materials
Present Status of the Fractesus Project: Round Robin on Unirradiated Materials Open
The present paper provides a summary of an inter-laboratory round robin on the fracture toughness testing and Master Curve application on unirradiated materials. First, a validation exercise was performed on the analysis of a given force-d…
View article: Master Curve Evaluation Using Miniature C(T) Specimens as Part of a Round Robin Program Within the FRACTESUS Project
Master Curve Evaluation Using Miniature C(T) Specimens as Part of a Round Robin Program Within the FRACTESUS Project Open
Surveillance testing is the basis for all reactor pressure vessel (RPV) integrity and lifetime assessments to evaluate the validity of the RPV embrittlement trend curve used for a specific reactor. Most of the standard surveillance program…
View article: Positron annihilation study of the reactor pressure vessel model steels irradiated in the high flux reactor
Positron annihilation study of the reactor pressure vessel model steels irradiated in the high flux reactor Open
Twelve reactor pressure vessel (RPV) model steels with parametric variation of alloying elements Ni and Mn were characterized by means of positron annihilation spectroscopy before and after irradiation at the High Flux Reactor (HFR) to ∼0.…
View article: The Main Results of Structural Materials Research for Safe Long-Term Operation of LWR NPPs from the Viewpoint of Dissemination Activities
The Main Results of Structural Materials Research for Safe Long-Term Operation of LWR NPPs from the Viewpoint of Dissemination Activities Open
One of the main points of any project implementation is the dissemination of the obtained results among the nuclear community, young researchers, public, stakeholders, etc. Communication and dissemination activities are considered as high-…
View article: Effectiveness of Thermal Annealing in Recovery of Tensile Properties of Compositionally Tailored PWR Model Steels Irradiated in LYRA-10
Effectiveness of Thermal Annealing in Recovery of Tensile Properties of Compositionally Tailored PWR Model Steels Irradiated in LYRA-10 Open
Understanding the mechanical behaviour of reactor pressure vessel (RPV) steels at high fluences has become an important topic in regard to Long-Term Operations (LTO) of existing nuclear power plants (NPP). The effectiveness of thermal anne…
View article: Neutron Irradiation Effects in 5xxx and 6xxx Series Aluminum Alloys: A Literature Review
Neutron Irradiation Effects in 5xxx and 6xxx Series Aluminum Alloys: A Literature Review Open
A literature review on highly irradiated 5xxx and 6xxx series Al alloys is conducted to understand the expected changes in mechanical properties of high flux reactor (HFR) vessel material in relation with microstructural aspects beyond the…