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Failure mode and effect analysis on ITER heat transfer systems
The complexity of the ITER (International Thermonuclear Experimental Reactor) plant and the inventories of radioactive materials involved in its operation require a systematic approach to perform detailed safety analyses during the various stages of the project in order to demonstrate compliance with the safety requirements. Expand
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The potential presence and minimisation of plutonium within the irradiated beryllium in fusion power plants
Abstract Beryllium is expected to be one of the materials used in DEMO-type fusion power plants as blanket neutron multiplier for solid breeders and also in ITER as protective layer of plasma facingExpand
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Ex-Vessel Break in ITER Divertor Cooling Loop Analysis with the ECART Code
A hypothetical double-ended pipe rupture in the ex-vessel section of the International Thermonuclear Experimental Reactor (ITER) divertor primary heat transfer system during pulse operation has beenExpand
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Characterization of the radiation field and evaluation of the nuclear responses in the ITER cryopump port cell
Abstract The ITER main vacuum system consists of six torus exhaust pumps integrated in the Cryostat through dedicated housings at the building B1 level. The Port Cell area outside the cryopump plugExpand
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ITER Reference Accidents
Abstract Reference accidents are selected to envelope possible accident sequences to confirm the adequacy of ITER's safety design. Analyses of ITER reference accidents were carried out starting fromExpand
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Collection and analysis of data related to fusion machines (JET and TLK) operating experience on component failure
This paper presents the summary of the activities related to data collection on the operating experiences gained in the Joint European Torus (JET) for the Vacuum and Active Gas Handling Systems (VS, AGHS) and in the Tritium Laboratory of Karlsruhe (TLK). Expand
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A First Approach to the Safety Analysis of a Tokamak Test Reactor by a System Study Methodology
The safety analysis and risk assessment of a Tokamak Test Reactor is approached by an iterative, probabilistic, system study methodology, jointly devoloped by ENEAa and CEAb. Expand
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Environmental Source terms during a few Reference Accident Sequences (RAS) of NET/ITER plant
This paper outlines the multi-code methodological approach foreseen to estimate the environmental releases of the activated corrosion/erosion products involved in accidents scenarios of a fusionExpand
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Source terms due to the activated corrosion products in primary cooling loops of ITER
Abstract This paper deals with the source terms due to the escape of activated corrosion products from a first wall or shielding blanket primary cooling loop of the international thermonuclearExpand
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Radiation transport and nuclear induced heating analysis for ITER baseline design
This paper presents the methodology calculation and the results of heat deposition due to the neutron and gamma interactions with the materials of different ITER zones. One dimensional discreteExpand
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