The role of spatial and temporal radiation deposition in inertial fusion chambers: the case of HiPER¿

The first wall armour for the reactor chamber of HiPER will have to face short energy pulses of 5 to 20 MJ mostly in the form of x-rays and charged particles at a repetition rate of 5–10 Hz. Armour material and chamber dimensions have to be chosen to avoid/minimize damage to the chamber, ensuring the proper functioning of the facility during its planned lifetime. The maximum energy fluence that the armour can withstand without risk of failure, is determined by temporal and spatial deposition of the radiation energy inside the material. In this paper, simulations on the thermal effect of the radiation–armour interaction are carried out with an increasing definition of the temporal and spatial deposition of energy to prove their influence on the final results. These calculations will lead us to present the first values of the thermo-mechanical behaviour of the tungsten armour designed for the HiPER project under a shock ignition target of 48 MJ. The results will show that only the crossing of the plasticity limit in the first few micrometres might be a threat after thousands of shots for the survivability of the armour

ITER breeding blanket design

A breeding blanket design has been developed for ITER to provide the necessary tritium fuel to achieve the technical objectives of the Enhanced Performance Phase. It uses a ceramic breeder and water coolant for compatibility with the ITER machine design of the Basic Performance Phase. Lithium zirconate and lithium oxide am the selected ceramic breeders based on the current data base. Enriched lithium and beryllium neutron multiplier are used for both breeders. Both forms of beryllium material, blocks and pebbles are used at different blanket locations based on thermo-mechanical considerations and beryllium thickness requirements. Type 316LN austenitic steel is used as structural material similar to the shielding blanket. Design issues and required R&D data are identified during the development of the design

Potential common radiation problems for components and diagnostics in future magnetic and inertial confinement fusion devices

This work aims at identifying common potential problems that future fusion devices will encounter for both magnetic (MC) and inertial (IC) confinement approaches in order to promote joint efforts and to avoid duplication of research

Du droit souple au droit dur : quel droit pour la qualité environnementale des vins sous indication géographique ?

Le droit du vin accompagne la réception par la filière viticole des valeurs de la Responsabilité Sociale et Environnementale. Les producteurs de vin et les pouvoirs publics recherchent un modèle plus éthique, plus performant sur le plan environnemental, compatible avec le développement durable. Les instruments juridiques utilisés ont beaucoup évolué en vingt ans. Dans un premier temps, les producteurs ont eu recours à des instruments volontaires, non contraignants, caractéristiques du droit souple (chartes éthiques, certification biologique, normes ISO). Une nouvelle règlementation est apparue en droit français. La loi prévoit, d'ici 2030, une certification environnementale, rendue obligatoire par le cahier des charges, pour tout producteur viticole exploitant sous signe de qualité (Appellation d'Origine Protégée ; Indication Géographique Protégée). Ce passage du droit volontaire (souple) au droit imposé (droit dur) est significatif de l'évolution fondamentale de la notion de qualité viticole, qui intègre la qualité environnementale. La qualité environnementale enrichit la qualité liée à l'origine

Thermal-Hydraulic Study of the ESPRESSO Blanket for a Tandem Mirror Reactor

This paper deals primarily with the thermal-hydraulic design and some critical thermomechanical aspects of the proposed ESPRESSO blanket for the Tandem Mirror Fusion Reactor. This conceptual design was based on the same physics as used in the MARS study

The Combined Effects of Magnetic Asymmetry, Assembly and Manufacturing Tolerances on the Plasma Heat Load to the ITER First Wall

Part of special issue: PLASMA-SURFACE INTERACTIONS 21: Proceedings of the 21st International Conference on Plasma-Surface Interactions in Controlled Fusion Devices Kanazawa, Japan May 26-30, 2014International audienceThe base plasma heat load on the ITER first wall results from the projection of the plasma scrape off layer power profile onto the shaped surface of the first wall panels. The actual heat load on the first wall is larger than the base heat load, due to enhancement factors such as design approximations, manufacturing and assembly errors, and deviations to the ideally toroidal magnetic field configurations. The heat load increase is accounted for through penalty coefficients, ranging individually from a few percent to 50%. The probabilistic combination of individual penalty coefficients to give a global penalty coefficient is presented in the paper. The global penalty coefficient ranges from 1.37 to 2.44, depending of the first wall row and plasma phase