A5006688138- Nuclear Materials and Properties
- Microstructure and Mechanical Properties of Steels
- Metal Forming Simulation Techniques
- Fatigue and fracture mechanics
- Metallurgy and Material Forming
- Nuclear and radioactivity studies
- Microstructure and mechanical properties
- Nuclear reactor physics and engineering
- High-Velocity Impact and Material Behavior
- Heat transfer and supercritical fluids
- Non-Destructive Testing Techniques
- Superconducting Materials and Applications
- High Temperature Alloys and Creep
- Magnetic confinement fusion research
- Fusion materials and technologies
- Titanium Alloys Microstructure and Properties
- Engineering Applied Research
- Material Properties and Failure Mechanisms
- Mechanical Failure Analysis and Simulation
- Risk and Safety Analysis
- Hydrogen embrittlement and corrosion behaviors in metals
- Nonlocal and gradient elasticity in micro/nano structures
- Metallurgical Processes and Thermodynamics
- Metal Alloys Wear and Properties
- Advanced ceramic materials synthesis
United Kingdom Atomic Energy Authority
2024
Territoires, Villes, Environnement & Société
2011-2024
Électricité de France (France)
2006-2023
Laboratoire de Mécanique des Sols, Structures et Matériaux
2007-2019
Direction de la Recherche Technologique
2017
Chimie Moléculaire, Macromoléculaire, Matériaux
2008-2012
Success of the UK’s Spherical Tokamak for Energy Production (STEP) programme requires a robust plasma control system. This system has to guide from initiation burning phase, maintain it there, produce desired fusion power duration and then terminate safely. be done in challenging environment with limited sensors without overloading plasma-facing components. The parameters operational regime STEP prototype will very different tokamaks, which are presently operation. During burn,...
Strain-aging constitutive models are suitable to simulate the formation and propagation of Lüders bands in complex specimens components. The identification corresponding material parameters is difficult because strain localization phenomena associated with behavior must be taken into account. spurious mesh dependence standard finite element simulations band illustrated present work removed using a gradient plasticity model. Furthermore approach introduces characteristic size dimension front...
The ALCYONE multidimensional fuel performance code codeveloped by the CEA, EDF, and AREVA NP within PLEIADES software environment models behavior of rods during irradiation in commercial pressurized water reactors (PWRs), power ramps experimental reactors, or accidental conditions such as loss coolant accidents reactivity-initiated (RIAs). As regards latter case transient particular, is intended to predictively simulate response a rod taking account mechanisms way that physics closely...
Abstract Control of heat exhaust is essential for the operation power producing fusion reactors. Here, we present results feedback control experiments in JET and AUG. In JET, demonstrate first X-point radiator (XPR) DD DT discharges using argon seeding. AUG, improve XPR with nitrogen seeding, resulting achieving detached L-H H-L transition (in a single discharge). The controllers are designed model-based design procedure. required models obtained experimentally perturbative (system...
This paper presents two case studies in which the use of full field measurements could provide valuable information to allow development R&D methods having potential assessing industrial issues.The first example is related study fracture properties nuclear fuel rods after a postulated Loss Coolant Accident (LOCA) event. It will be shown that 3-D Digital Image Correlation strain performed on non-conventional mechanical test (expansion due compression) can help assess failure and derive...
For western pressure vessel reactors, assessment of steels irradiation embrittlement due to neutron is based on a semi-empirical formulae which predicts the shift reference lower bound fracture toughness curve as function fluence and embrittlement-involved chemical elements. Periodically, in order monitor each RPV, predictions confronted experimental results obtained from Charpy specimens located surveillance capsules irradiated with higher level than itself. Historically only temperature...
Abstract Because of the carbon macro-segregation inherent to large thickness flat component manufacturing, Fracture Mechanics Assessment (FMA) Steam Generator Tube-Sheet (SG-TS) was required for flaws postulated close primary (and cladded) surface or secondary (non-cladded) in France. For those assessments, a flaw relying two holes is postulated, which represents singular configuration compared conventional FMA. Indeed relatively small comparison plate and crack length limited by distance...
The monitoring of neutron induced embrittlement nuclear power plants is provided using Charpy impact test in the surveillance program. However structural integrity assessments require fracture toughness. Some empirical formulas have been developed but no direct relationship was found. aim our study to determine toughness a Reactor Pressure Vessel steel from instrumented local approach fracture. This non-empirical method has applied brittle domain as well ductile transition for an A508 C1.3...
The Reactor Pressure Vessel (RPV) is with the concrete containment one of two components a NPP whose replacement not considered as reasonably feasible. RPV lifetime has thus an important impact on whole NPP. One key issues concerning radiation effect steel in core zones. vessel becomes indeed more brittle region where high. Margins have been included at design and manufacturing stages taking into account material’s embrittlement. Moreover, operating measures taken to manage ageing order...
Cold-work stress-relieved Zircaloy-4 kinetics of recovery-recrystallization has been studied under dynamic conditions. A specific furnace dilatometer was used to heat specimens up 430 ∘C⋅s−1. Comparison results with data isothermal recovery and recrystallization showed that the process is delayed when heating rate increased. model proposed describe evolution material unrecrystallized fraction during rapid anisothermal transients. Comparisons a good agreement between experimental predictions.
The objective of the present paper is to review crack front length effect (also called “specimen size effect”) on Fracture Toughness PWR Reactor Pressure Vessel Steel base metal. analysis reality and amplitude this conducted in a first step database (the so “GKSS database”) including fracture toughness test results single representative material using specimens different thicknesses, tested same temperature range. A realistic analytical form for describing observed data set thus derived from...
Abstract In the frame of a Fracture Mechanics Assessement in perforated part steam-generator tubesheet, defect relying two holes is postulated, which represent singular configuration compared to conventional FMA. Indeed relatively small comparison plate thickness and crack length limited by distance between holes. To take benefit geometry effect this configuration, an application parameters J-Q approach performed on tubesheet component. At first, methodology was applied define validate...