Search Results - "Ricapito, I"
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An overview of the EU breeding blanket design strategy as an integral part of the DEMO design effort
Published in Fusion engineering and design (01-04-2019)“…•The performance and reliability of the breeding blanket are foremost considerations in the development and deployment of fusion power.•No breeding blanket has…”
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2
Lead–lithium eutectic material database for nuclear fusion technology
Published in Journal of nuclear materials (15-06-2008)“…Fully validated material databases are needed for coherent technological developments in any R&D field. For nuclear fusion technology (NFT), within a near-term…”
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Journal Article Conference Proceeding -
3
European TBM programme: First elements of RoX and technical performance assessment for DEMO breeding blankets
Published in Fusion engineering and design (01-07-2020)“…•European TBM Programme (description).•European DEMO Breeding Blanket Programme (description).•Technical Requirements on the Breeding blanket for DEMO.•TBM…”
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Overview of the ITER TBM Program
Published in Fusion engineering and design (01-08-2012)“…► The ITER TBM Program is the answer to the ITER mission of “testing tritium breeding module concepts that would lead in a future reactor to tritium…”
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5
Supporting analysis for WCLL test blanket system safety
Published in Fusion engineering and design (01-12-2021)“…•Safety studies to support the integration of the WCLL TBSs into ITER are presented.•A MELCOR model developed to perform safety studies on ITER WCLL TMB is…”
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6
Experimental campaign on pressure wave propagation in LLE
Published in Fusion engineering and design (01-11-2018)“…•Results of 5 tests simulating In-box LOCA in the LLE loop of HCLL TBM are presented.•The facility is a mock-up of the LLE loop of the HCLL TBM.•The maximum…”
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7
Experimental investigation on HCLL-TBS In-box LOCA
Published in Fusion engineering and design (01-09-2019)“…The experimental facility THALLIUM was designed and installed at ENEA C.R. Brasimone to investigate the consequence of a HCLL-TBS In box LOCA, ensuring the…”
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Investigation on efficiency of gas liquid contactor used as tritium extraction unit for HCLL-TBM Pb-16Li loop
Published in Fusion engineering and design (01-11-2016)“…•A dedicated facility, called TRIEX was manufactured in order to investigate the tritium extraction efficiency of GLC as TEU (Tritium Extraction Unit) of…”
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Preliminary assessment of tritium permeation and retention in the European Water Cooled Lithium Lead Test Blanket Module with TESSIM-X
Published in Nuclear materials and energy (01-09-2022)“…•T inventory in the ITER EU Water-Cooled Lithium-Lead Test Blanket Module investigated.•T from vacuum vessel (gas, neutrals) and solute T in PbLi included in…”
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10
Tritium technologies and transport modelling: main outcomes from the European TBM Project
Published in Fusion engineering and design (01-11-2018)“…The tritium technologies and transport modelling play an essential role for the achievement of the TBM Programme scientific objectives. Tritium technologies…”
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Experimental and RELAP5-3D results on IELLLO (Integrated European Lead Lithium LOop) operation
Published in Fusion engineering and design (01-11-2017)“…•Analysis of the behavior of the main components of the loop.•Testing of a pressure transducer and a Vortex mass flow meter for use in LLE…”
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12
Technologies and modelling issues for tritium processing in the European Test Blanket Systems and perspectives for DEMO
Published in Fusion engineering and design (01-10-2014)“…•Provided DEMO relevancy considerations on tritium processing technologies.•Provided updates on the main technologies present in the Test blanket System…”
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13
Updated design and integration of the ancillary circuits for the European Test Blanket Systems
Published in Fusion engineering and design (01-09-2019)“…The validation of the key technologies relevant for a DEMO Breeding Blanket is one of the main objectives of the design and operation of the Test Blanket…”
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14
Conceptual design of Tritium Extraction System for the European HCPB Test Blanket Module
Published in Fusion engineering and design (01-08-2012)“…► HCPB (Helium Cooled Pebble Bed) Test Blanket Module (TBM) to be tested in ITER. ► Tritium extraction by gas purging, removal and transfer to the Tritium…”
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15
Finalization of the conceptual design of the auxiliary circuits for the European test blanket systems
Published in Fusion engineering and design (01-10-2015)“…In view of the ITER conceptual design review, the design of the ancillary systems of the European test blanket systems presented in [1] has been updated and…”
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Progresses and challenges in supporting activities toward a license to operate European TBM systems in ITER
Published in Fusion engineering and design (01-10-2014)“…•First EUROFER steel design limits have been introduced in RCC-MRx.•Preliminary fabrication/welding procedure specifications for the European TBM box are under…”
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17
Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop
Published in Fusion engineering and design (01-10-2015)“…•RELAP5-3D model of He-FUS3 facility and turbo circulator (TC).•Cold and hot facility T/H numerical analysis for the TC operanting range.•Effect of the cold…”
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Strategy for the development of EU Test Blanket Systems instrumentation
Published in Fusion engineering and design (01-10-2013)“…•We developed a strategy for the development of instrumentation for EU ITER TBSs.•TBSs instrumentation functions: safety, operation and scientific…”
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Tritium breeder blankets design and technologies in Europe: Development status of ITER Test Blanket Modules, test & qualification strategy and roadmap towards DEMO
Published in Fusion engineering and design (01-12-2010)“…Europe has developed two reference tritium breeder blankets concepts that will be tested in ITER under the form of Test Blanket Modules: (i) the Helium-Cooled…”
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Journal Article Conference Proceeding -
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Mechanical and corrosion behaviour of EUROFER 97 steel exposed to Pb–17Li
Published in Journal of nuclear materials (01-12-2002)“…Corrosion and tensile samples of the EUROFER 97 steel were exposed to Pb–17Li in the LIFUS II loop at 480 °C. The specimens were extracted after 1500, 3000 and…”
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