L. Affinito

National Agency for New Technologies, Energy and Sustainable Economic Development

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A. della Corte

National Agency for New Technologies, Energy and Sustainable Economic Development

L. Muzzi

National Agency for New Technologies, Energy and Sustainable Economic Development

S. Turtù

Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Frascati

A. Di Zenobio

National Agency for New Technologies, Energy and Sustainable Economic Development

V. Corato

National Agency for New Technologies, Energy and Sustainable Economic Development

A. Anemona

National Agency for New Technologies, Energy and Sustainable Economic Development

S. Chiarelli

National Agency for New Technologies, Energy and Sustainable Economic Development

Chiarasole Fiamozzi Zignani

National Agency for New Technologies, Energy and Sustainable Economic Development

R. Freda

National Agency for New Technologies, Energy and Sustainable Economic Development

P. Bruzzone

École Polytechnique Fédérale de Lausanne

Cooperative Institutions

National Agency for New Technologies, Energy and Sustainable Economic Development

204

Weatherford College

166

Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Frascati

University of Rome Tor Vergata

ENEA Frascati Research Centre

Royal Military Academy

University of Padua

Culham Science Centre

Institute for the Science and Technology of Plasmas

Culham Centre for Fusion Energy

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Magnetic and Electromechanical Characterization of a High-J_C RRP Wire for the HL-LHC MQXF Cable

IEEE Transactions on Applied Superconductivity (2022)

G. De Marzi B. Bordini L. Muzzi L. Affinito A. Angrisani Armenio

In this work, we summarize the results of a series of inductive and transport measurements aimed at the evaluation of the electromechanical performance of a 0.85 mm diameter RRP wire procured for the HL-LHC project. The critical current dependence on the magnetic field and uniaxial applied strain (between −0.2 and 0.5%) has been investigated in a temperature range between 4.5 K and 10 K. Furthermore, the wire magnetization up to 12 T has been measured at different temperatures (4.3 K–14 K) to determine the wire's effective filament diameter and to complement the critical current density in the temperature and field range where transport current measurements were not available. The experimental results have been analysed in the framework of the Extrapolative Scaling Expression, by using a multi-step approach for the data fitting. These results provide an accurate parameterization of the critical surface in terms of field, temperature and strain, and can be used as a general reference for magnet design.

Niobium-tin

Atmospheric temperature range

10.1109/tasc.2022.3167655

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Citations (5)

Design and Manufacture of a NbTi Insert Module Relevant for the ITER PF Magnets Conductor

Elsevier eBooks (2005)

A. della Corte L. Affinito S. Chiarelli P. Gislon Gabriele Messina

Insert (composites)

Niobium-tin

Realization (probability)

10.1016/b978-008044559-5/50136-8

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Citations (0)

Preparation of PF1/6 and PF2 Conductor Performance Qualification Sample

IEEE Transactions on Applied Superconductivity (2010)

L. Reccia S. Turtù Gian Mario Polli L. Affinito F. Maierna

The ITER Conductor Procurement Arrangement requires that all the conductors have to be qualified before the production phase. The objects of the work here presented are the Poloidal Field Coils conductors, specifically the PF1/6 and the PF2 conductors. The realization of the samples comprised the jacketing, the compaction and the straightening of the CICC, together with the design and manufacturing of the bottom hairpin box and the upper termination. The instrumentation and the related jacket machining completed the preparation of the samples. The samples have been assembled according to the specification defined by ITER and have been shipped to SULTAN facility. This paper describes all the activities performed during the preparation, the features of the samples and all the related issues.

Instrumentation

Realization (probability)

10.1109/tasc.2010.2081963

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Citations (8)

Test of the ENEA Joint With a NbTi Large CiC Conductor

IEEE Transactions on Applied Superconductivity (2013)

Chiarasole Fiamozzi Zignani L. Affinito S. Chiarelli A. della Corte A. Di Zenobio

This paper describes the results of the measurements performed in June 2011 on a NbTi cable-in-conduit conductor curved joint in the ENEA Superconductivity Laboratories (C.R. Frascati). The effectiveness of the joint design, patented by ENEA, had been already verified for the $\hbox{Nb}_{3} \hbox{Sn}$ EDIPO conductor; in this case, it has been applied to a NbTi cable-in-conduit conductor. The joint was manufactured and instrumented by ENEA, using part of a JT-60SA toroidal field conductor sample (namely the TFCRS) produced by Luvata Italy and successfully tested in SULTAN. For testing purposes, the NbTi “shaking hands”-type joint was hosted in a variable temperature cryostat with a background superconducting magnet. The sample was used as the secondary coil of a transformer having the background magnet as primary coil. Measurements were preceded by preliminary code simulation studies computed in the Matlab workspace, and by 3-D finite element method analyses, to estimate the test requirements and its feasibility. The joint resistance value, found to be less than 2 $\hbox{n}\Omega$ has been derived both by the sample current decay time constant evaluation and by calorimetric calculations. After a short description of the joint design and fabrication, as well as of the test instrumentation and geometry, the joint resistance evaluation will be presented, together with the data analysis procedures and results.

Niobium-tin

Cryostat

10.1109/tasc.2013.2239334

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Citations (0)

DTT: Divertor Tokamak Test facility Project Proposal

L. Affinito A. Anemona M.L. Apicella P. Batistoni G. Calabrò

One of the main challenges in the European fusion roadmap is to design a heat and power exhaust system able to withstand the large loads expected in the divertor of a DEMO fusion power plant. Therefore, in parallel with the programme to optimise the operation with a conventional divertor based on detached conditions to be tested on the ITER device currently under construction in Cadarache, a specific project has been launched to investigate alternative power exhaust solutions for DEMO, aimed at the definition and the design of a Divertor Tokamak Test facility. This tokamak should be capable of hosting scaled experiments integrating most of the possible aspects of the DEMO power and particle exhaust. DTT should retain the possibility to test different divertor magnetic configurations, liquid metal divertor targets, and other possible solutions for the power exhaust problem. The DTT design proposal refers to a set of parameters selected so as to have edge conditions as close as possible to DEMO (in terms of the temperature and the normalized collisionality, pressure and ion gyro radius), while remaining compatible with DEMO bulk plasma performance in terms of dimensionless parameters within a set of constraints related to flexibility and costs

Collisionality

Fusion power

Source

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Citations (9)

Conference Author Index

IEEE Transactions on Applied Superconductivity (2022)

Atsushi Abe L. Affinito K. Agari A. Ahl A Akella

10.1109/tasc.2022.3198770

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Citations (0)

DTT - Divertor Tokamak Test facility - Interim Design Report

L. Affinito S. Almaviva A. Anemona M. Angelone M.L. Apicella

Interim

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Citations (52)

Overview of Conductor Production for ITER Toroidal Field Magnet in Korea

IEEE Transactions on Applied Superconductivity (2013)

Soo-Hyeon Park Soun Pil Kwon Won Woo Park Hee Kyoung Choi Young Jae

The ITER toroidal field (TF) conductor is made up of superconducting Nb ₃ Sn and copper strands assembled into a multistage, rope-type cable inserted into a conduit of butt-welded stainless steel jacket sections. For the ITER Project, the Korean Domestic Agency (KODA) took the responsibility of the procurement of 27 superconducting conductors for the ITER TF magnets. After concluding the Procurement Arrangement (PA) with the ITER International Organization in May 2008, KODA has been implementing the PA through four major industrial contracts: (1) Nb ₃ Sn strand, (2) cable, (3) stainless steel jacket sections, and (4) jacketing. Prior to the production of conductors required for the TF coils, one 760-m-long copper dummy conductor and one 100-m-long superconducting conductor were fabricated for manufacturing process qualification. As of June 2013, 16 TF conductors were successfully manufactured. The full-size conductor performance tests in the SULTAN facility yielded very high performance. This article describes the technical requirements of the TF conductor and how KODA has been manufacturing the conductors with a high-level quality assurance/quality control system. It also presents the results of acceptance tests, including those of the SULTAN test.

Niobium-tin

Acceptance testing

Toroidal field

10.1109/tasc.2013.2283173

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Citations (8)

DC Test Results of the DEMO TF React&Wind Conductor Prototype No. 2

IEEE Transactions on Applied Superconductivity (2019)

Kamil Sedlák P. Bruzzone B. Stepanov R. Wesche Xabier Sarasola

In 2013, the EUROfusion organization launched the preconceptual design studies of the fusion DEMO tokamak. Several options of superconducting magnet design are investigated within the scope of the project. The magnets based on Nb ₃ Sn, namely the Toroidal Field (TF) and Central Solenoid (CS) coils, can be made either using the Wind&React technology, as in ITER, or React&Wind (RW) technology with potentially significant cost-saving benefits. Within the R&D program of the Swiss Plasma Center, the first full-size DEMO TF RW conductor prototype, RW1, was manufactured and tested in 2015-2016. The second, improved prototype, RW2, was built and tested in 2017-2018. The experimental results collected over several test campaigns performed on four assemblies of RW2 rated for 63 kA at 12.23 T are presented. The current sharing temperature T _cs of the latest RW2 assembly in DEMO operating conditions reached 7.16 K after 1000 electromagnetic cycles and four thermal cycles. This T _cs corresponds to the effective strain ε _eff = -0.27%, significantly exceeding the design requirement of T _cs ≥ 6.7 K. If RW2 have been used in ITER TF coils, the T _cs at 68 kA and 10.9 T would be 7.42 K, i.e., approximately 1 K higher than most of the ITER TF samples, and that with only 55% of Nb ₃ Sn used in ITER TF conductor. The tests of RW2 proved that the cost-saving potential of the React&Wind technology is enormous.

Solenoid

10.1109/tasc.2019.2901130

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Citations (19)

PRELIMINARY DESIGN OF 30 KA CURRENT LEADS FOR THE ENEA CICC UPGRADED TEST FACILITY

AIP conference proceedings (2010)

G. M. Polli L. Affinito A. della Corte A. Di Zenobio L. Muzzi

An upgrade of the CICC facility at the ENEA Superconductivity laboratories for the characterization of superconducting long length wound conductors in forced He flow cooling, has begun. In this framework a considerable effort has been spent for the design of two appropriate gas‐cooled current leads for a 30 kA insert. Indeed, several geometrical and operational constraints have been considered due to the re‐use of the pre‐existing cryogenic plant and background magnet. In particular, to limit the overall length of the leads and the amount of cooling gas to be employed, a hybrid resistive/HTS configuration has been conceived. It consists of a copper bar, with an adequate heat exchanger, from room temperature down to 40 K and an HTS BSCCO part from 40 K down to 5 K. Two helium inlets are foreseen for the lead cooling: one at 5 K at the bottom edge, in parallel to the background magnet refrigerant line, and one at 16 K in the joint between the resistive and the HTS parts. In this paper the description of the numerical analyses performed for the optimal design of the leads are discussed.

Upgrade

Cryogenics

Resistive touchscreen

10.1063/1.3422404

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Citations (1)