A5022774422- Nuclear Materials and Properties
- Nuclear Engineering Thermal-Hydraulics
- Nuclear reactor physics and engineering
- Fatigue and fracture mechanics
- Nuclear and radioactivity studies
- Probabilistic and Robust Engineering Design
- Fusion materials and technologies
- Metallurgy and Material Forming
- Metal Forming Simulation Techniques
- Graphite, nuclear technology, radiation studies
- High Temperature Alloys and Creep
- Fire effects on concrete materials
- High-Velocity Impact and Material Behavior
- Engineering Applied Research
- Laser and Thermal Forming Techniques
- Microstructure and Mechanical Properties of Steels
- Magnetic confinement fusion research
- Advanced Algebra and Logic
- Mechanical Failure Analysis and Simulation
- Material Properties and Applications
- Structural Health Monitoring Techniques
- Non-Destructive Testing Techniques
- Hydrogen embrittlement and corrosion behaviors in metals
- Plant Ecology and Soil Science
- Structural Integrity and Reliability Analysis
Institute for Nuclear Research Pitesti
2010-2025
University of Pitesti
2014-2019
Lucian Blaga University of Sibiu
2016-2017
Structural Integrity Associates (United States)
2014
The Zr-2.5%Nb alloy used to manufacture the pressure tubes for CANDU 600 power plant experiences continual corrosion when reactor’s fuel channels are functioning normally. Analysis of hydrogen accumulation circumstances, creation zirconium hydride platelets, evaluation platelets’ reorientation in thermo–mechanical field at volumetric flaws, and determination morphology therefore significant goals worldwide research being conducted this field. In paper, tube samples with artificial V flaws...
The pressure tubes of the CANDU 600 nuclear power plant at CNE Cernavoda Romania are made Zr-2.5%Nb alloy, which is susceptible to hydrogen accumulation during normal operation. As part work, structural integrity analyses will be performed regarding initiation Delayed Hydride Cracking (DHC) phenomenon complex flaws in tubes, can detected by periodic inspections on fuel channels. These described Canadian standard CAN/CSA N285.8 as a combination Bearing Pad Fretting Flaw (BPFF) with Debris...
The concerns about the availability of energy resources, climate change, air quality, and security suggest important role that nuclear power has in future supply. While current Generation II III types plants provide an economically acceptable source electricity for many markets, advances design IV systems may expand opportunities use energy. Research-Development-Innovation activity carried out by RATEN ICN regarding is focused, through several research directions, on development ALFRED...
Romania, through RATEN ICN, is involved in the construction of ALFRED demonstrator (Advanced Lead Fast Reactor European Demonstrator), which core reactor uses cooling liquid lead environment. This constitutes one arguments for development studies on innovative materials generation IV, having stated objective problem contact between and structural specific to this type reactor. The purpose paper highlight changes thermomechanical behaviour induced by 316L austenitic steel lead, as well its...
"Zirconium alloys are used in heavy water-cooled reactors due to their low thermal neutron capture cross-section and good mechanical corrosion properties. At the beginning of operation, hydrogen was identified as an embrittlement agent. The source hydride precipitates that formed platelets. Hydrides were associated with cracks process called Delayed Hydride Cracking – DHC. This research aims develop a reproducible procedure concerning DHC KIH parameter measurements on Zirconium claddings, by...
The assessment of fatigue crack growth due to turbulent mixing hot and cold coolants presents significant challenges, in particular determine the thermal loading spectrum. Thermal striping is defined as a random temperature fluctuation produced by incomplete fluid streams at different temperatures, it essentially phenomenon temporal sense. objective this work develop stochastic model assess tees, based on power spectral density (PSD) inner pipe surface. Based analytical solution for...
The present paper focuses on analyzing the forming capacity of steel blanks with hydroforming process. For this research sheets have been in focus for numerical and experimental analysis. main advantages materials are good surface finish, excellent close tolerances, appealing manufacturers. A finite element model has developed from data obtained through tensile tests limit curves. newly press used to carry out experiments. Side-by-side analysis between results concludes experiment.
The present paper describes the current status of hydroforming technology in today’s global market that focuses on energy use respect to increasing requirements especially from automotive industry with its renaissance after economic crisis. A vast classification and restrictions drawbacks for a wider share are also presented.
Abstract Designing a die is in every application field an intensive process of bringing together know how from design, testing and every-day use previous dies with the new requirements. Contribution deals knowledge oriented, modular feature integrated computer aided design system for development. This paper describes concepts behind designing hydroforming sheet metal forming, easy application-use small workshops capabilities different materials.
Abstract Pellet cladding mechanical interaction (PCMI) is a potential failure mechanism for fuel claddings during Reactivity Initiated Accident (RIA) type event, thus preventing of the material transient conditions considered one primary safety criteria to ensure element integrity. Eight irradiation experiments aimed validate experimental setup and test methodology developed in frame MAXSIMA (Methodology, Analysis eXperiments Safety In MYRRHA Assessment) project have been carried out Annular...
The Zr-2.5%Nb alloy, from which the pressure tubes of CANDU 600 power plant at Cernavodă NPP are made, is permanently subjected to a corrosion process during normal operation fuel channels in reactor. At same time, formation specific flaws on inner surface tube under conditions prolonged irradiation and absorption deuterium cooling agent, heavy water, leads initiation precursor centers for cracking mechanical load, called specialized literature type Delayed Hydride Cracking (DHC). Among...
The paper aims to investigate the mechanical properties of tubes having a small diameter and made from new steels called ODS Oxide Dispersion Strengthened steels). These materials are candidate for fuel claddings in generation IV reactors. This work contributes original results experimental program carried out by RATEN ICN Pitesti framework FP7 European MatISSE Project (Materials� Innovations Safe Sustainable nuclear �n Europe). method used investigating steel is non-standard method, known...