A5086782541- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Atomic and Molecular Physics
- Laser-induced spectroscopy and plasma
- Fusion materials and technologies
- Graphite, nuclear technology, radiation studies
- Magnetic confinement fusion research
- Nuclear Materials and Properties
- Laser-Plasma Interactions and Diagnostics
- Nuclear and radioactivity studies
- Plasma Diagnostics and Applications
- Advanced Chemical Physics Studies
- Radiation Therapy and Dosimetry
- Particle accelerators and beam dynamics
- Mass Spectrometry Techniques and Applications
- Superconducting Materials and Applications
- Radiation Detection and Scintillator Technologies
- Stellar, planetary, and galactic studies
- Nuclear physics research studies
- Ionosphere and magnetosphere dynamics
- Spectroscopy and Laser Applications
- Cold Atom Physics and Bose-Einstein Condensates
- Cold Fusion and Nuclear Reactions
- Laser-Matter Interactions and Applications
- Spectroscopy and Quantum Chemical Studies
National University of Distance Education
2015-2024
Distance State University
2024
École Polytechnique
1997-2010
Laboratoire pour l'utilisation des lasers intenses
1997-2010
Sorbonne Université
1997-2010
Centre National de la Recherche Scientifique
1997-2010
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
1999-2010
Czech Academy of Sciences, Institute of Physics
2008-2010
Université de Bordeaux
2008-2010
Centre Lasers Intenses et Applications
2008-2010
Abstract The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutron-induced interactions with the major actinides $$^{235}\hbox {U}$$ <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"><mml:mrow><mml:msup><mml:mrow /><mml:mn>235</mml:mn></mml:msup><mml:mtext>U</mml:mtext></mml:mrow></mml:math> , $$^{238}\hbox /><mml:mn>238</mml:mn></mml:msup><mml:mtext>U</mml:mtext></mml:mrow></mml:math> $$^{239}\hbox {Pu}$$...
Abstract ITER is of key importance in the European fusion roadmap as it aims to prove scientific and technological feasibility a future energy source. The EUROfusion consortium labs within Europe contributing preparation exploitation operation aspires exploit outcomes view DEMO. paper provides an overview major progress obtained recently, carried out frame new (initiated 2021) work-package called ‘ Pr eparation I TER O peration’ (PrIO). directly supported by eleven PrIO contributions given...
The GEOUNED code is specifically designed to convert CAD models, defined using the B-rep approach, into MC radiation transport CSG and vice versa from CAD. This incorporates standard features commonly found in conversion tools, including decomposition, conversion, automatic void generation. Additionally, it introduces innovative features, mainly generation part, which are described this article. has demonstrated successful application highly detailed 3D models used fusion neutronics, known...
R2SUNED is a code system implementing the mesh-based Rigorous-two-step method for shutdown dose rates calculations, making use of MCNP and ACAB codes. In addition to most relevant features state-of-the-art R2S systems, novel unique have been implemented in overcome limitations common current implementations. One particular interest cell-under-voxel approach intended address issues associated with conventional averaging technique used neutron flux determination. The underlying idea identify...
Abstract During ITER operational life, a remote-handled cask will be used to transfer In-Vessel components the Hot Cell for maintenance, storage and decommissioning purposes. Due distribution of penetrations system allocation in facility, radiation field each operation presents high spatial variability; all operations must studied independently workers electronics protection. In this paper, we present fully representative approach describe environment during complete remote-handling scenario...
One of the primary goals ITER project is to demonstrate safety characteristics a fusion device, particularly in terms radiation management. Radiation protection during maintenance periods special concern, as personnel performing maintenance‐like activities will be exposed delayed gamma fields from numerous and complex radioactive components. Ensuring safe equipped environment for such objective hot cell. This facility requires extensive design optimization, balancing spatial temporal...
The methodological approach employed for the neutronics in PPPT (Power Plant Physics and Technology) programme of EUROfusion is presented. It encompasses development works on advanced computational tools activities related to nuclear design performance evaluation DEMO power plant including safety, maintenance, waste management issues. Development work conducted Monte Carlo codes, CAD geometry conversion simulations, coupled radiation transport activation computation systems. role data...
Neutronics benchmark experiments are conducted at JET in the frame of WPJET3 NEXP within EUROfusion Consortium for validating neutronics codes and tools used ITER nuclear analyses to predict quantities such as neutron flux along streaming paths dose rates shutdown due activated components. The preparation rate future Deuterium-Tritium operations (DTE2 campaign) progress. This paper summarizes status measurements progress current Deuterium–Deuterium (DD) campaign efforts DTE2.
The ITER Tokamak Complex is the civil structure that will host and largest part of associated systems. dimensions are 120 m × 80 60 m, built mostly concrete, with over one thousand penetrations. During operation, a radiation field spread throughout complex from diverse sources. It must be characterized to check compliance limits for electronics allocation human intervention. However, production maps in task paramount sophistication due challenges adequately model MCNP sources involved. In...
ITER reference MCNP models are the portentous result of years geometric modelling, and they share bio-shield as natural boundary for practical reasons. Models representing Tokamak, or fractions it, end in bio-shield. Those Tokamak Complex start Nuclear analysis beyond is high relevance to forecast radiation conditions electrical electronic equipment, well human intervention, affecting both economics safety. Nevertheless, it presents a challenge when dealing with plasma source: source not...
A preliminary beam dump cartridge design has been proposed recently for the IFMIF-EVEDA accelerator. Copper was material chosen stop. In this paper we investigate possibility of designing a practical shielding so that it can offer an acceptable radioprotection response during both beam-on and beam-off phases. The analysis is performed whole component located inside already designed accelerator vault. comprehensive methodology to deal with problem. Special attention paid treatment neutron...
A novel multiphysics methodology for the computation of realistic plasma neutron sources has been developed. The method is based on state-of-the-art transport and spectrum calculations, coupled with a Monte Carlo code, bridging gap between physics neutronics. In paper two JET neutronics tokamak models are used to demonstrate application developed validate them. Diagnostic data record D discharge 92436 as input TRANSP modelling emission in external heating scenarios, namely using only neutral...
During ITER operations, electronics located in the crane hall, which is above tokamak, will be exposed to neutron and photon fields from both plasma activated water. To protect electronics, implementation of dedicated shielding on hall platform bioshield top lid required. The design demands optimisation attending constructability, weight limits, radiation requirements. This work evaluates eight configurations by assessment flux dose accumulated over 4700 h operation at 500 MW for protection....
The ITER equatorial port plugs are submitted to a drained weight limit of 45 T. This limitation can conflict with their radiation shielding demands, although some margin is being discussed. interspaces subject shutdown dose rate 100 µSv h−1 after 106 s cooling time. To meet it, the must show neutron flux attenuation comparable neighborhood, despite considering penetrations host systems. Most this task relies on drawer shield module (DSM). In work, two DSM concepts analyzed perspective:...