Assessment of operational space for long-pulse scenarios in ITER
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May 2015 |
Integrated simulations of H-mode operation in ITER including core fuelling, divertor detachment and ELM control
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March 2018 |
Surface‐limited release of deuterium from tantalum
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March 1991 |
An overview on tritium permeation barrier development for WCLL blanket concept
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August 2004 |
Sieving hydrogen isotopes through two-dimensional crystals
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December 2015 |
Tritium transport modeling at system level for the EUROfusion dual coolant lithium-lead breeding blanket
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August 2017 |
Measurement of hydrogen isotope concentration in erbium oxide coatings
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October 2014 |
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems
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August 2020 |
Observation of enhanced ion particle transport in mixed H/D isotope plasmas on JET
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June 2018 |
Pellet fuelling and control of burning plasmas in ITER
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May 2007 |
Analysis of low pressure hydrogen separation from fusion exhaust gases by the means of superpermeability
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November 2017 |
Impact of Outer Fuel Cycle Tritium Transport on Initial Start-Up Inventory for Next Fusion Devices
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August 2019 |
Irradiation of liquid breeder material Pb17Li with in-situ tritium release measurements in the LIBRETTO 2 experiment
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March 1991 |
Tritium Modeling for ITER Test Blanket Module
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October 2015 |
Consequences of the technology survey and gap analysis on the EU DEMO R&D programme in tritium, matter injection and vacuum
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November 2016 |
Technology Development for Isotope Rebalancing and Protium Removal in the EU-DEMO Fuel Cycle
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April 2020 |
Physics basis for the first ITER tungsten divertor
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August 2019 |
The ITER Tokamak Exhaust Processing System Design and Substantiation
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journal
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August 2019 |
The issue of Tritium in DEMO coolant and mitigation strategies
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September 2020 |
SOLPS-ITER modelling of ITER edge plasma with drifts and currents
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March 2020 |
Effect of conditions for gas recirculation on divertor operation in ITER
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June 2007 |
Myth of initial loading tritium for DEMO—Modelling of fuel system and operation scenario
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October 2017 |
Design of a Permeator-Against-Vacuum mock-Up for the tritium extraction from PbLi at low speed
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October 2017 |
In-pile performance of a double-walled tube and a tritium permeation barrier
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December 2002 |
A New Approach for Assessing the Required Tritium Breeding Ratio and Startup Inventory in Future Fusion Reactors
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May 1999 |
Influence of Oxygen on Permeation of Hydrogen Isotopes Through Group 5 Metals
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August 2008 |
The KALPUREX-process – A new vacuum pumping process for exhaust gases in fusion power plants
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October 2014 |
Materials-related issues in the safety and licensing of nuclear fusion facilities
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June 2017 |
ELM flushing and impurity transport in the H-mode edge barrier in ASDEX Upgrade
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August 2011 |
Matter injection technology for DEMO, state of the art
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November 2017 |
A Dynamic Modeling 3H Transfer to the Environment Under Accidental Release from the Fusion Reactor
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February 2015 |
The surface rate constants of deuterium in the martensitic steel DIN 1.4914 (MANET)
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May 1995 |
Fuelling and density control for DEMO
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September 2015 |
Effect of transonic flow in the ablation cloud on the lifetime of a solid hydrogen pellet in a plasma
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January 1978 |
Results of an International Study on a High-Volume Plasma-Based Neutron Source for Fusion Blanket Development
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January 1996 |
Tritium Transport in Fusion Reactor Materials
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August 2020 |
High‐speed repeating hydrogen pellet injector for long‐pulse magnetic confinement fusion experiments
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May 1996 |
Progress in the ITER Physics Basis
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June 2007 |
The Direct Internal Recycling concept to simplify the fuel cycle of a fusion power plant
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October 2013 |
Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER
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August 2017 |
Overview of the DEMO staged design approach in Europe
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April 2019 |
Analysis of the EU-DEMO fuel cycle elements: Intrinsic impact of technology choices
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November 2018 |
Tritium/hydrogen barrier development
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March 1995 |
Development of Advanced Exhaust Pumping Technology for a DT Fusion Power Plant
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April 2014 |
A new HCPB breeding blanket for the EU DEMO: Evolution, rationale and preliminary performances
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November 2017 |
The ITER tritium systems
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October 2007 |
Overview of recent developments in pellet injection for ITER
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August 2012 |
Enhanced configuration of a water detritiation system; impact on ITER Isotope Separation System based cryogenic distillation
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November 2016 |
Advancements in DEMO WCLL breeding blanket design and integration: Advancements in DEMO WCLL breeding blanket design and integration
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May 2017 |
Water Detritiation System for ITER—Evaluation of Design Parameters
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March 2017 |
Comparison of fueling efficiency from different fueling locations on DIII-D
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March 2003 |
Tritium supply and use: a key issue for the development of nuclear fusion energy
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November 2018 |
Progress of the R&D programme to develop a metal foil pump for DEMO
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December 2020 |
Verification and Validation of the Tritium Transport Code TMAP7
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August 2005 |
Breeding blanket system design implications on tritium transport and permeation with high tritium ion implantation: A MATLAB/Simulink, COMSOL integrated dynamic tritium transport model for HCCR TBS
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November 2018 |
Multi-machine analysis of termination scenarios with comparison to simulations of controlled shutdown of ITER discharges
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journal
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December 2017 |
Progress in the blanket neutronics experiments at JAERI/FNS
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journal
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February 2006 |
Numerical analyses for conceptual design of an irradiation PbLi capsule for testing of protective coatings for the European DEMO breeding blanket project
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November 2018 |
Tritium fuel cycle modeling and tritium breeding analysis for CFETR
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journal
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May 2016 |
Physics and technology conditions for attaining tritium self-sufficiency for the DT fuel cycle
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February 2006 |
Neutral recirculation—the key to control of divertor operation
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September 2016 |
Experimental investigation of alumina coating as tritium permeation barrier for molten salt nuclear reactors
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November 2019 |
Hydrogen in 304 steel: Diffusion, permeation and surface reaction
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July 1987 |
Non-linear MHD modelling of ELM triggering by pellet injection in DIII-D and implications for ITER
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April 2014 |
Tritium supply assessment for ITER and DEMOnstration power plant
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October 2013 |
Analysis of performance of the optimized divertor in ITER
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May 2009 |
Tritium transport analysis in HCPB DEMO blanket with the FUS-TPC code
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October 2013 |
Core Fueling of DEMO by Direct Line Injection of High-Speed Pellets From the HFS
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journal
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May 2018 |
DEMO tritium fuel cycle: performance, parameter explorations, and design space constraints
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journal
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April 2019 |
Analysis of fuelling requirements in ITER H-modes with SOLPS-EPED1 derived scalings
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September 2016 |
Pellet-Injector Technology—Brief History and Key Developments in the Last 25 Years
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December 2017 |
Review of Hydrogen Isotope Permeability Through Materials
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August 1983 |
Sensitivity analysis of tritium breeding ratio and startup inventory for CFETR
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November 2016 |
Main Features of the Technology for Air Detritiation in Scrubber Column
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November 2016 |
Tritium management and safety issues in ITER and DEMO breeding blankets
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October 2013 |
The rate of hydrogen release out of clean metallic surfaces
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September 1978 |
Fusion reactor start-up without an external tritium source
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February 2016 |
Correlation between Hydrogen Isotope Permeation through Niobium and Bulk Oxygen Concentration: Possible Influence of Oxygen on Tritium Recovery from Pb-Li by Vacuum Permeator
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November 2007 |
Status of Pb-16Li technologies for European DEMO fusion reactor
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September 2019 |
Tritium permeation barriers for fusion technology
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journal
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March 1995 |
First result of deuterium retention in neutron-irradiated tungsten exposed to high flux plasma in TPE
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August 2011 |
Analysis of Tritium/Deuterium Retention and Permeation in FW/Divertor Including Geometric and Temperature Operating Features
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August 2013 |
The effect of inert gas pre-irradiation on the retention of deuterium in tungsten: A TMAP investigation combined with first-principles method
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journal
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October 2017 |
A smart three-loop fuel cycle architecture for DEMO
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journal
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September 2019 |
Deuterium transport in SiCf/SiC composites
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journal
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December 2002 |
Feasibility analysis of vacuum sieve tray for tritium extraction in the HCLL test blanket system
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journal
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November 2016 |
Integrated core-SOL modelling of fuelling, density control and divertor heat loads for the flat-top phase of the ITER H-mode D-T plasma scenarios
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journal
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December 2018 |
Fuel flow and stock during deuterium-deuterium start-up of fusion reactor with advanced plasma model
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journal
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November 2020 |
In-pile tritium release behaviour of lithiummetatitanate produced by extrusion–spheroidisation–sintering process in EXOTIC-9/1 in the high flux reactor, Petten
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journal
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October 2007 |
An international pellet ablation database
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April 1997 |
Experimental investigation on charcoal adsorption for cryogenic pump application
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December 2017 |
Deuterium-Tritium Fuel Self-Sufficiency in Fusion Reactors
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March 1986 |
Uncertainties in Prediction of Tritium Breeding in Candidate Blanket Designs Due to Present Uncertainties in Nuclear Data Base
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March 1986 |
High fusion power steady state operation in JET DT plasmas
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August 1999 |
Analysis on tritium controlling of the dual-cooled lithium lead blanket for fusion power reactor FDS-II
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June 2009 |
Physics requirements on fuel throughput in ITER
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August 2011 |
Diffusive transport parameters and surface rate constants of deuterium in Incoloy 800
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January 2002 |
Metal Foil Pump performance aspects in view of the implementation of Direct Internal Recycling for future fusion fuel cycles
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November 2018 |
Tritium Transport Evolutions in HCCR TBM Under ITER Inductive Operations
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September 2015 |
Preparation technique and alloying effect of aluminide coatings as tritium permeation barriers: A review
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March 2015 |
Japan Atomic Energy Research Institute/United States Integral Neutronics Experiments and Analyses for Tritium Breeding, Nuclear Heating, and Induced Radioactivity
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August 1995 |
Tritium issues to be solved for establishment of a fusion reactor
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August 2012 |
The coolant purification system in DEMO: Interfaces and requirements
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November 2017 |
Impurity seeding in ITER DT plasmas in a carbon-free environment
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August 2015 |
Tritium aspects of the fusion nuclear science facility
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October 2018 |
Pellet injection as a possible tool for plasma performance improvement
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September 2003 |
Advancement in tritium transport simulations for solid breeding blanket system
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November 2016 |
Considerations on the DEMO pellet fuelling system
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October 2015 |
Plasma enhancement gases (PEGs) separation using a carbon molecular sieve (CMS) membrane
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September 2019 |
CAD-based interface programs for fusion neutron transport simulation
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June 2009 |
Basic divertor operation in ITER-FEAT
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February 2002 |
Tritium Plant Technology Development for a DEMO Power Plant
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journal
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March 2017 |
The density dependence of edge-localized-mode suppression and pump-out by resonant magnetic perturbations in the DIII-D tokamak
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December 2019 |
High-density H-mode operation achieved using efficient plasma refueling by inboard pellet launch
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March 2001 |
Safety assessment of two advanced ferritic steel molten salt blanket design concepts
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November 2004 |
LIBRETTO-3: Performance of tritium permeation barriers under irradiation at the HFR Petten
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September 1994 |
Tritium production assessment for the DCLL EUROfusion DEMO
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August 2016 |
Simplified mass ablation and relocation treatment for pellet injection optimization
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October 2001 |
Particle transport analysis of the density build-up after the L–H transition in ASDEX Upgrade
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August 2013 |
Permeation of hydrogen through nickel foils: surface reaction rates at low temperatures
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August 1991 |
Preliminary interpretation of the LIBRETTO-2 experimental results in terms of tritium permeation barrier efficiency
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Applications of superpermeable membranes in fusion: The flux density problem and experimental progress
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February 1997 |
Characterization of ZAO® sintered getter material for use in fusion applications
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September 2019 |
Transport of tungsten in the H-mode edge transport barrier of ITER
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November 2014 |
Recent results on the fuelling and control of plasmas by pellet injection, application to ITER
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November 2009 |
Zeolite membranes and palladium membrane reactor for tritium extraction from the breeder blankets of ITER and DEMO
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October 2013 |
Ceramic membranes for processing plasma enhancement gases
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November 2017 |
Hisotope thermo-diffusion in structural materials
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November 2017 |
A model for tritium transport in fusion reactor components: The FUS-TPC code
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May 2012 |
Neoclassical transport of impurities in tokamak plasmas
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September 1981 |
Characteristics and scaling of energy and particle losses during Type I ELMs in JET H-modes
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Impact of pellet injection on extension of the operational region in LHD
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April 2001 |
Tritium resources available for fusion reactors
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December 2017 |
Optimization process for the design of the DCLL blanket for the European DEMOnstration fusion reactor according to its nuclear performances
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May 2017 |
Advanced design of the Mechanical Tritium Pumping System for JET DTE2
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November 2016 |
Influence of the surface conditions on permeation in the deuterium–MANET system
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February 1997 |
Blanket/first wall challenges and required R&D on the pathway to DEMO
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November 2015 |
The enhanced ASDEX Upgrade pellet centrifuge launcher
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October 2013 |
Analysis on Initial Tritium Supply for Starting Up Fusion Power Reactor FDS-II
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October 2011 |
Particle transport in tokamak plasmas, theory and experiment
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November 2009 |
Hydrogen isotopes transport parameters in fusion reactor materials
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June 1998 |
The CECE Alternative for Upgrading/Detritiation in Heavy Water Nuclear Reactors and for Tritium Recovery in Fusion Reactors
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Comparison of deuterium pellet injection from different locations on the DIII-D tokamak
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October 2007 |
Case study on tritium inventory in the fusion DEMO plant at JAERI
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February 2006 |
The surface rate constants of deuterium in the reduced activating martensitic steel OPTIFER-IVb
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December 2000 |
Modelling of the pellet deposition profile and ∇ B -induced drift displacement in non-axisymmetric configurations
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November 2012 |
MHD stability of the ITER pedestal and SOL plasma and its influence on the heat flux width
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August 2015 |
Power exhaust in tokamaks and scenario integration issues
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November 2017 |
Compatibility of pellet fuelling with ELM suppression by RMPs in the ASDEX Upgrade tokamak
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April 2020 |