Paul lez Durance

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Keywords: ITER Gas injection system R&D GIS response time Magnetic shield design a b s t r a c t The gas injection system (GIS) is an indispensable part of ITER fueling system. It deliveries the necessary gas species from tritium plant to vacuum vessel, pellet injection system or neutral beam for plasma operation and fusion power shutdown. In this paper,(More)
In order to validate PWR depletion calculation routes and cycle length prediction, an extensive PIE Programme was launched in the framework of the CEA-EdF-Framatome collaboration 1. The fuel inventory calculation was mainly qualified through the analysis of fuel irradiated 2-3 cycles in Bugey3 and 4-5 cycles in Fessenheim2 (3.1% U235 enrichment), and fuel(More)
Experiments in Alcator C-Mod in EDA H-modes with extrinsic impurity seeding (N 2 , Ne, Ar) have demonstrated a direct correlation between plasma energy confinement and edge power flow achieving values of H 98 ≥ 1 for edge power flows only marginally exceeding the scaled power for access to H-mode confinement in these conditions. For lower Z impurity seeding(More)
The purpose of the work is to review interim results of the Joint Study on assessment of an Innovative Nuclear System based on a Closed Nuclear Fuel Cycle with Fast Reactors (INS CNFC-FR). This study is a part of the IAEA international project for innovative reactors and fuel cycle technologies (INPRO). results of implementation of the first phase of the(More)
The poloidal field (PF) coil system on ITER, which provides both feedforward and feedback control of plasma position, shape, and current, is a critical element for achieving mission performance. Analysis of PF capabilities has focused on the 15 MA Q = 10 scenario with a 300-500 s flattop burn phase. The operating space available for the 15 MA ELMy H-mode(More)
The recent package APOLLO2.8-MOC/CEA2005-SHEM developed by CEA is undergoing a large validation program. First works of development and validation of a new optimized calculation scheme called REL2005-based on the Method of Characteristics-are presented in this paper. The comparison of APOLLO2.8/REL2005 results to reference Monte Carlo TRIPOLI4 ones on(More)
This paper deals with the H∞ stabilization of the spatial distribution of the current profile of tokamak plasmas using a Linear Matrix Inequalities (LMIs) approach. The control design is based on the one dimensional resistive diffusion equation of the magnetic flux that governs the plasma current profile evolution. The feedback control law is derived in the(More)
Assessment of plasma parameters is carried out for low activation phase required for commissioning the basic ITER systems including plasma control, heating and current drive, etc. Such operation is analyzed for hydrogen , helium and deuterium plasmas for full field and current as well as with magnetic field and plasma current reduced to half of their design(More)
241 P u resonance parameters in the energy range thermal to 20 eV. Abstract This paper presents a new SAMMY analysis of the 241 P u resonance parameters from thermal to 20 eV. This evaluation takes into account the trends given by integral experiments (Post-Irradiation Experiments performed in French PWR). Compared to the previous evaluations performed by(More)
The ITER Ion Cyclotron Resonance Frequency (ICRF) antenna is required to couple 20MW through fast (sub-ms) changes in loading during Edge Localised Modes (ELM's). The chosen design comprises a port plug supporting a close-packed array of 24 straps which are connected in triplets to eight transmission lines fed via 3dB couplers or a conjugate-T(More)