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Conceptual design of a PAV-based tritium extractor for the WCLL breeding blanket of the EU DEMO: Effects of surface-limited vs. diffusion-limited modeling

Fusion engineering and design, 2021-06, Vol.167, p.112363, Article 112363

2021

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Coupling and Hysteresis Loss Measurements on the ITER CS Module #4

IEEE transactions on applied superconductivity, 2024-05, Vol.34 (3), p.1-5

2024

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Engineering design of a Permeator Against Vacuum mock-up with niobium membrane

Fusion engineering and design, 2021-05, Vol.166, p.112313, Article 112313

2021

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Integrated deterministic and probabilistic safety assessment of a superconducting magnet cryogenic cooling circuit for nuclear fusion applications

Reliability engineering & system safety, 2020-09, Vol.201, p.106945, Article 106945

2020

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Thermal-hydraulic analysis of the DTT CS and PF pulsed coil performance during AC operation

Fusion engineering and design, 2021-12, Vol.173, p.112836, Article 112836

2021

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Analysis of the Thermal-Hydraulic Effects of a Plasma Disruption on the DTT TF Magnets

IEEE transactions on applied superconductivity, 2022-09, Vol.32 (6), p.1-7

2022

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Prediction, experimental results and analysis of the ITER TF insert coil quench propagation tests, using the 4C code

Superconductor science & technology, 2018-01, Vol.31 (3), p.35004

2018

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AC Losses in the Second Module of the ITER Central Solenoid

IEEE transactions on applied superconductivity, 2022-09, Vol.32 (6), p.1-5

2022

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Progress in the design of the superconducting magnets for the EU DEMO

Fusion engineering and design, 2018-11, Vol.136, p.1597-1604

2018

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Analysis of the cooldown of the ITER central solenoid model coil and insert coil

Superconductor science & technology, 2017-01, Vol.30 (1), p.15015

2017

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Thermal Hydraulic Behavior of the First ITER CS Module

IEEE transactions on applied superconductivity, 2021-08, Vol.31 (5), p.1-5

2021

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DTT: A Challenging Framework for a Sound Superconducting Magnets Design

IEEE transactions on applied superconductivity, 2022-09, Vol.32 (6), p.1-5

2022

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Coupling superconducting magnet and refrigerator thermal-hydraulic models for nuclear fusion applications

IOP conference series. Materials Science and Engineering, 2019-04, Vol.502 (1), p.12130

2019

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Incorporating Artificial Neural Networks in the dynamic thermal–hydraulic model of a controlled cryogenic circuit

Cryogenics (Guildford), 2015-09, Vol.70, p.9-20

2015

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Overview of Progress on the EU DEMO Reactor Magnet System Design

IEEE transactions on applied superconductivity, 2016-06, Vol.26 (4), p.1-5

2016

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Characterization of the ITER CS conductor and projection to the ITER CS performance

Fusion engineering and design, 2017-11, Vol.124, p.1-5

2017

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Full‐core coupled neutronic/thermal‐hydraulic modelling of the EBR‐II SHRT‐45R transient

International journal of energy research, 2018-01, Vol.42 (1), p.134-150

2018

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DTT device: Conceptual design of the superconducting magnet system

Fusion engineering and design, 2017-11, Vol.122, p.299-312

2017

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A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors

Nuclear engineering and design, 2013-08, Vol.261, p.85-94

2013

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Validation of the 4C Thermal-Hydraulic Code Against 25 kA Safety Discharge in the ITER Toroidal Field Model Coil (TFMC)

IEEE transactions on applied superconductivity, 2011-06, Vol.21 (3), p.1948-1952

2011

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Numerical analysis of propagation of thermal disturbances in brass-stabilized REBCO tapes

Cryogenics (Guildford), 2016-12, Vol.80, p.390-399

2016

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Artificial Neural Network (ANN) modeling of the pulsed heat load during ITER CS magnet operation

Cryogenics (Guildford), 2014-09, Vol.63, p.231-240

2014

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4C modeling of the supercritical helium loop HELIOS in isobaric configuration

Cryogenics (Guildford), 2014-11, Vol.64, p.51-62

2014

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Thermal-Hydraulic Simulation of 80 kA Safety Discharge in the ITER Toroidal Field Model Coil (TFMC) Using the 4C Code

IEEE transactions on plasma science, 2012-03, Vol.40 (3), p.782-787

2012

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4C code analysis of thermal–hydraulic transients in the KSTAR PF1 superconducting coil

Cryogenics (Guildford), 2013-01, Vol.53, p.37-44

2013

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Conceptual design of a PAV-based tritium extractor for the WCLL breeding blanket of the EU DEMO: Effects of surface-limited vs. diffusion-limited modeling

Coupling and Hysteresis Loss Measurements on the ITER CS Module #4

Engineering design of a Permeator Against Vacuum mock-up with niobium membrane

Integrated deterministic and probabilistic safety assessment of a superconducting magnet cryogenic cooling circuit for nuclear fusion applications

Thermal-hydraulic analysis of the DTT CS and PF pulsed coil performance during AC operation

Analysis of the Thermal-Hydraulic Effects of a Plasma Disruption on the DTT TF Magnets

Prediction, experimental results and analysis of the ITER TF insert coil quench propagation tests, using the 4C code

AC Losses in the Second Module of the ITER Central Solenoid

Progress in the design of the superconducting magnets for the EU DEMO

Analysis of the cooldown of the ITER central solenoid model coil and insert coil

Thermal Hydraulic Behavior of the First ITER CS Module

DTT: A Challenging Framework for a Sound Superconducting Magnets Design

Coupling superconducting magnet and refrigerator thermal-hydraulic models for nuclear fusion applications

Incorporating Artificial Neural Networks in the dynamic thermal–hydraulic model of a controlled cryogenic circuit

Overview of Progress on the EU DEMO Reactor Magnet System Design

Characterization of the ITER CS conductor and projection to the ITER CS performance

Full‐core coupled neutronic/thermal‐hydraulic modelling of the EBR‐II SHRT‐45R transient

DTT device: Conceptual design of the superconducting magnet system

A full-core coupled neutronic/thermal-hydraulic code for the modeling of lead-cooled nuclear fast reactors

Validation of the 4C Thermal-Hydraulic Code Against 25 kA Safety Discharge in the ITER Toroidal Field Model Coil (TFMC)

Numerical analysis of propagation of thermal disturbances in brass-stabilized REBCO tapes

Artificial Neural Network (ANN) modeling of the pulsed heat load during ITER CS magnet operation

4C modeling of the supercritical helium loop HELIOS in isobaric configuration

Thermal-Hydraulic Simulation of 80 kA Safety Discharge in the ITER Toroidal Field Model Coil (TFMC) Using the 4C Code

4C code analysis of thermal–hydraulic transients in the KSTAR PF1 superconducting coil

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