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The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European - Japanese project towards a Li(d,xn) fusion relevant neutron source
TLDR
The International Fusion Materials Irradiation Facility (IFMIF), presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase under the frame of the Broader Approach Agreement between Europe and Japan, accomplished in summer 2013, on schedule, its EDA phase with the release of the engineering design report of the IFMIF plant, which is here described. Expand
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Effects of nuclear interactions on energy and stopping power in proton beam dosimetry
Abstract Most experimental methods for proton beam dosimetry require stopping power values and proton energy distributions in the irradiated materials. At proton energies of interest in radiotherapy,Expand
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Neutronics of the IFMIF-DONES irradiation facility
Abstract The methodological approach applied for the nuclear analyses of the IFMIF-DONES facility, developed within the Early Neutron Source (ENS) project of EUROfusion, is presented. It utilizesExpand
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On the Figure of Merit in Neutron Time-of-Flight Measurements
Abstract We address the task of evaluating the basic performances of neutron time-of-flight spectrometers, by means of an appropriate figure of merit. Calculations of neutron flux, energy resolution,Expand
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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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The European contribution to the development and validation activities for the design of IFMIF lithium facility
Abstract The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-driven intense neutron source where candidate materials for fusion reactors will be tested and validated.Expand
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The New Sorgentina Fusion Source-NSFS: 14 MeV neutrons for fusion and beyond
The importance of the design for the realization of an intense 14 MeV neutron facility devoted to test and validate materials suitable for harsh neutron environments, such as a fusion reactor, isExpand
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Analysis of the thermomechanical behavior of the IFMIF bayonet target assembly under design loading scenarios
Abstract In the framework of the IFMIF Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) phase, ENEA is responsible for the design of the European concept of the IFMIF lithiumExpand
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Preliminary evaluation of the expected radiation damage of the bayonet IFMIF back-plate
Abstract This paper summarises and discusses the results of a preliminary damage assessment of the non-seizure coating of the bayonet IFMIF back-plate. Neutron-induced kerma factors, dpa and gasExpand
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Neutronics and activation calculation for ITER generic site safety report
This paper focuses on some of the response functions obtained from a Sn radiation transport and activation analysis, namely the nuclear heating, decay heat and clearance index due to the neutronExpand
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