| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Access to an ELM-suppressed X-point radiator regime in TCV snowflake minus configurations
|
Reimerdes, H.
|
|
|
41 |
C |
p.
|
artikel
|
| 2 |
A new attempt to further reduce the work function of the cesiated surface: The strongest electronegative element fluorine co-adsorption with cesium on Mo (001) surface
|
Li, Heng
|
|
|
41 |
C |
p.
|
artikel
|
| 3 |
An understanding of the segregation and migration mechanism of point defects in tungsten grain boundaries: An atomic scale simulation
|
Li, Ya-Wen
|
|
|
41 |
C |
p.
|
artikel
|
| 4 |
A reduced cluster dynamics modeling of radiation damage in tungsten
|
Li, Zhiyuan
|
|
|
41 |
C |
p.
|
artikel
|
| 5 |
Assessing the toroidal radiation distribution at Wendelstein 7-X by combining Gaussian Process Tomography and field line mapping
|
Partesotti, G.
|
|
|
41 |
C |
p.
|
artikel
|
| 6 |
A study on initial formation stage of proton irradiation defects in reactor pressure vessel steel
|
Hao, Ting
|
|
|
41 |
C |
p.
|
artikel
|
| 7 |
Asymmetry in particle load on divertor tiles in different magnetic field configurations of LHD
|
Sugiyama, Tsukasa
|
|
|
41 |
C |
p.
|
artikel
|
| 8 |
Calculation of in-situ steady-state heat flux on EAST lower divertor
|
He, Chunyu
|
|
|
41 |
C |
p.
|
artikel
|
| 9 |
Coexistence of H-MAR and N-MAR in divertor simulation experimental module of GAMMA 10/PDX
|
Okamoto, T.
|
|
|
41 |
C |
p.
|
artikel
|
| 10 |
Collisional-Radiative modeling of unresolved transition array spectra near 200 Å from W17+-W25+ emissions for diagnostics of ITER edge plasma
|
Nishimura, R.
|
|
|
41 |
C |
p.
|
artikel
|
| 11 |
Corrigendum to “Comparative analysis of gas release from biphasic lithium ceramics pebble beds of various pebbles sizes and content under neutron irradiation conditions” [Nucl. Mater. Energy 38 (2024) 101583]
|
Kulsartov, Timur
|
|
|
41 |
C |
p.
|
artikel
|
| 12 |
Corrigendum to “The brittle-to-ductile transition in cold-rolled tungsten sheets: Contributions of grain and subgrain boundaries to the enhanced ductility after pre-deformation” [Nucl. Mater. Energy 25 (2020) 100769]
|
Bonnekoh, Carsten
|
|
|
41 |
C |
p.
|
artikel
|
| 13 |
2D analysis of tokamak divertor-plasma detachment-bifurcation with operational parameters and geometries
|
Zhao, M.
|
|
|
41 |
C |
p.
|
artikel
|
| 14 |
Density compensation with pellet fueling during ELM suppression with n = 4 RMP on metal-wall EAST tokamak
|
Hou, Jilei
|
|
|
41 |
C |
p.
|
artikel
|
| 15 |
Designing tungsten armoured plasma facing components to pulsed heat loads in magnetic fusion machines
|
Mitteau, R.
|
|
|
41 |
C |
p.
|
artikel
|
| 16 |
Detachment scalings derived from 1D scrape-off-layer simulations
|
Body, Thomas
|
|
|
41 |
C |
p.
|
artikel
|
| 17 |
Deuterium retention in displacement-damaged tungsten-rhenium alloys: Influence of rhenium concentration and irradiation temperature
|
Zibrov, M.
|
|
|
41 |
C |
p.
|
artikel
|
| 18 |
Development of ITER first wall heat load feedback control
|
Pesamosca, Federico
|
|
|
41 |
C |
p.
|
artikel
|
| 19 |
Divertor erosion at ASDEX Upgrade during helium plasma operations
|
Vuoriheimo, Tomi
|
|
|
41 |
C |
p.
|
artikel
|
| 20 |
Divertor tungsten source monitoring by A visible spectroscopy diagnostic on EAST
|
Ding, Fang
|
|
|
41 |
C |
p.
|
artikel
|
| 21 |
Edge plasma turbulence simulations in detached regimes with the SOLEDGE3X code
|
Quadri, V.
|
|
|
41 |
C |
p.
|
artikel
|
| 22 |
Effective control of intrinsic impurities using n = 1 resonant magnetic perturbation (RMP) in EAST H-mode plasma
|
Zhang, Wenmin
|
|
|
41 |
C |
p.
|
artikel
|
| 23 |
Effect of helium on micro-fracture strength for multi-ion-irradiated F82H by micro-tensile testing
|
Ando, Masami
|
|
|
41 |
C |
p.
|
artikel
|
| 24 |
Effect of oxygen or copper impurities on the work function of cesiated surfaces under co-existence with hydrogen: A study about negative hydrogen ion sources for neutral beam injection systems
|
Li, Heng
|
|
|
41 |
C |
p.
|
artikel
|
| 25 |
Enhanced thermomechanical fatigue resistance in W10Re alloys: Microstructural and surface engineering approaches
|
Sommerauer, Michael
|
|
|
41 |
C |
p.
|
artikel
|
| 26 |
Establishing the temperature and orientation dependence of the threshold displacement energy in ThO2 via molecular dynamics simulations
|
Yu, Lin-Chieh
|
|
|
41 |
C |
p.
|
artikel
|
| 27 |
Evaluation of local erosion and deposition on the W-monoblock of JA-DEMO divertor
|
Oya, M.
|
|
|
41 |
C |
p.
|
artikel
|
| 28 |
Evaluation of thermal properties of CuCrFeV (Ti, Ta, W, Mo) for nuclear fusion applications
|
Rodríguez-López, A.
|
|
|
41 |
C |
p.
|
artikel
|
| 29 |
Evolution and cleaning of the deposit layers on the lower divertor of WEST fully equipped with ITER grade components
|
Gerardin, J.
|
|
|
41 |
C |
p.
|
artikel
|
| 30 |
Experimental characterization of leading edge cracking on bulk tungsten divertor components during 2017–2019 WEST operation
|
Diez, M.
|
|
|
41 |
C |
p.
|
artikel
|
| 31 |
Experimental insights on iron-based alloys corrosion in water cooled loops
|
Molinari, Martina
|
|
|
41 |
C |
p.
|
artikel
|
| 32 |
Experimental investigation of steady state power balance in double null and single null H mode plasmas in MAST Upgrade
|
Lovell, J.
|
|
|
41 |
C |
p.
|
artikel
|
| 33 |
Experimental observations of bifurcated power decay lengths in the near Scrape-Off Layer of ST40 High Field Spherical Tokamak
|
Zhang, X.
|
|
|
41 |
C |
p.
|
artikel
|
| 34 |
Experimental study on metallic impurity behavior with boronization wall conditioning in EAST tokamak
|
Cheng, Yunxin
|
|
|
41 |
C |
p.
|
artikel
|
| 35 |
Fabrication and characterization of novel high-efficiency and high-durability neutron-absorbing Ni-based alloys
|
Pan, Jie
|
|
|
41 |
C |
p.
|
artikel
|
| 36 |
Fast prediction of irradiation-induced cascade defects using denoising diffusion probabilistic model
|
Liao, Ruihao
|
|
|
41 |
C |
p.
|
artikel
|
| 37 |
First integrated core-edge fluid simulation of ITER’s Limiter–Divertor transition with SolEdge-HDG
|
d’Abusco, M. Scotto
|
|
|
41 |
C |
p.
|
artikel
|
| 38 |
First SOLEDGE3X-EIRENE simulations of the ITER Neon seeded burning plasma boundary up to the first wall
|
Sureshkumar, S.
|
|
|
41 |
C |
p.
|
artikel
|
| 39 |
Full-torus impurity transport simulation in boron powder injection experiments in the Large Helical Device
|
Shoji, M.
|
|
|
41 |
C |
p.
|
artikel
|
| 40 |
Full W ITER: Assessment of expected W erosion and implications of boronization on fuel retention
|
Schmid, K.
|
|
|
41 |
C |
p.
|
artikel
|
| 41 |
Global 3D full-scale turbulence simulations of TCV-X21 experiments with SOLEDGE3X
|
Bufferand, H.
|
|
|
41 |
C |
p.
|
artikel
|
| 42 |
HEAT simulation and IR data comparison for ST40 plasma-facing components
|
Tinacba, E.J.C.
|
|
|
41 |
C |
p.
|
artikel
|
| 43 |
Helium retention feature in the boron deposited layer on tungsten substrate by laser-induced breakdown spectroscopy and machine learning approach
|
Shabbir, Muhammad Amir
|
|
|
41 |
C |
p.
|
artikel
|
| 44 |
ICRF-specific W sources: Advances in minimization in ASDEX Upgrade and near-field based extrapolations to ITER with W-wall
|
Bobkov, V.
|
|
|
41 |
C |
p.
|
artikel
|
| 45 |
Identification of a double decay length ( λ q t ) heat flux deposition shape with embedded thermal measurement and neural network
|
Anquetin, Y.
|
|
|
41 |
C |
p.
|
artikel
|
| 46 |
Implementation of a non-axisymmetric magnetic configuration in SOLEDGE3X to simulate 3D toroidal magnetic ripple effects: Application to WEST
|
Düll, Raffael
|
|
|
41 |
C |
p.
|
artikel
|
| 47 |
Improved erosion estimates for the STEP divertor
|
Kirschner, A.
|
|
|
41 |
C |
p.
|
artikel
|
| 48 |
Impurity behaviour in JET high-current baseline scenario for Deuterium, Tritium and Deuterium-Tritium plasmas
|
Wendler, N.
|
|
|
41 |
C |
p.
|
artikel
|
| 49 |
Inferring the scrape-off layer heat flux width in a divertor with a low degree of axisymmetry
|
Marsden, C.
|
|
|
41 |
C |
p.
|
artikel
|
| 50 |
Influence of phase decomposition on mechanical properties and oxidation resistance of WCrY SMART material
|
Chen, Jie
|
|
|
41 |
C |
p.
|
artikel
|
| 51 |
Influence of suppressed blistering by heavy ion pre-damage on deuterium retention in tungsten
|
Wang, Ting
|
|
|
41 |
C |
p.
|
artikel
|
| 52 |
Initial design concepts for solid boron injection in ITER
|
Snipes, J.A.
|
|
|
41 |
C |
p.
|
artikel
|
| 53 |
In search of X-point radiator regime features in NSTX and DIII-D discharges with the snowflake divertor
|
Soukhanovskii, V.A.
|
|
|
41 |
C |
p.
|
artikel
|
| 54 |
In-situ monitoring of tungsten oxides reduction during deuterium plasma exposure by spectroscopic ellipsometry
|
Pappalardo, F.
|
|
|
41 |
C |
p.
|
artikel
|
| 55 |
Investigating the effect of BT direction on W source-to-core pathways during the SAS-VW campaign on DIII-D
|
Mateja, J.D.
|
|
|
41 |
C |
p.
|
artikel
|
| 56 |
Investigation of H-mode density limit in mixed protium–deuterium plasmas at JET with ITER-like wall
|
Huber, A.
|
|
|
41 |
C |
p.
|
artikel
|
| 57 |
Investigation of spatial distribution characteristics of emission intensity in detachment on the divertor simulator TPDsheet-ICR
|
Tonegawa, A.
|
|
|
41 |
C |
p.
|
artikel
|
| 58 |
Investigation of the interaction of deuterium with Sn73Li27 tin-lithium alloy
|
Kulsartov, T.
|
|
|
41 |
C |
p.
|
artikel
|
| 59 |
LIA-QMS method for the quantity analysis of the hydrogen isotopes retention in first-wall components of Globus-M2 tokamak
|
Medvedev, O.S.
|
|
|
41 |
C |
p.
|
artikel
|
| 60 |
Liquid lithium divertor analysis using coupled plasma material interaction model
|
Khodak, Andrei
|
|
|
41 |
C |
p.
|
artikel
|
| 61 |
Lithium vapor cave design considerations
|
Emdee, E.D.
|
|
|
41 |
C |
p.
|
artikel
|
| 62 |
Lyman line opacities in tokamak divertor plasmas under high-recycling and detached conditions
|
Chandra, Ray
|
|
|
41 |
C |
p.
|
artikel
|
| 63 |
Melting behaviour of mixed plutonium and iron oxides: An experimental study
|
Casini, Luca
|
|
|
41 |
C |
p.
|
artikel
|
| 64 |
Metallic droplet impact simulations on plasma-facing components
|
Vignitchouk, L.
|
|
|
41 |
C |
p.
|
artikel
|
| 65 |
Micro-mechanical evaluations of adhesion properties for Cr-coated accident tolerant fuel cladding
|
Hong, Jong-Dae
|
|
|
41 |
C |
p.
|
artikel
|
| 66 |
Modeling a divertor with mid-leg pumping for high-power H-mode scenarios in DIII-D considering E × B drift flows
|
Holm, Andreas
|
|
|
41 |
C |
p.
|
artikel
|
| 67 |
Modelling of particle-reflection-distributions of rough surfaces
|
von Toussaint, U.
|
|
|
41 |
C |
p.
|
artikel
|
| 68 |
Molecular dynamic simulations of displacement cascades in molybdenum and molybdenum-rhenium alloys
|
Wang, Xudong
|
|
|
41 |
C |
p.
|
artikel
|
| 69 |
Molecular dynamics study of interstitial He clusters in nickel
|
Nandipati, Giridhar
|
|
|
41 |
C |
p.
|
artikel
|
| 70 |
Normal high velocity solid dust impacts on tiles of tokamak-relevant temperature
|
De Angeli, Marco
|
|
|
41 |
C |
p.
|
artikel
|
| 71 |
Numerical simulation of E × B drift effects on fueling pellet ablation and transport in EAST
|
Wang, Weikang
|
|
|
41 |
C |
p.
|
artikel
|
| 72 |
Post-mortem analysis of material deposition and fuel retention on the plasma-facing materials after the 2021 campaign in EAST
|
Zheng, Wei
|
|
|
41 |
C |
p.
|
artikel
|
| 73 |
Post-mortem analysis of the deposit layers on the lower divertor after the 2023 high particle fluence campaign of WEST
|
Martin, C.
|
|
|
41 |
C |
p.
|
artikel
|
| 74 |
Predicting image processing-normalized DL-EPRT performance from Rudimentary Cihal method-based counterpart
|
Alshater, Abdulla F.
|
|
|
41 |
C |
p.
|
artikel
|
| 75 |
Predicting the stability and exploring the fundamental physical properties of tetragonal Gd2O3: A comprehensive first-principles investigation
|
Islam, Minhajul
|
|
|
41 |
C |
p.
|
artikel
|
| 76 |
Properties of boron layers deposited during boronisations in W7-X
|
Mayer, M.
|
|
|
41 |
C |
p.
|
artikel
|
| 77 |
Quantitative analysis of impurities deposited on the Plasma-Facing Components of EAST tokamak using a portable LIBS device
|
Hu, Zhenhua
|
|
|
41 |
C |
p.
|
artikel
|
| 78 |
Quantitative analysis of transmutation nuclides in pure tungsten irradiated with high-energy protons and spallation neutrons at 6.4 and 28 dpa
|
Araullo-Peters, Vicente
|
|
|
41 |
C |
p.
|
artikel
|
| 79 |
Recent progress in the development of liquid metal plasma facing components for magnetic fusion devices
|
Hu, J.S.
|
|
|
41 |
C |
p.
|
artikel
|
| 80 |
Removal of deuterium retention by various helium discharge cleanings under strong magnetic field in EAST superconducting tokamak
|
Yu, Yaowei
|
|
|
41 |
C |
p.
|
artikel
|
| 81 |
Repair of heat load damaged plasma–facing material using the wire-based laser metal deposition process
|
Tweer, Jannik
|
|
|
41 |
C |
p.
|
artikel
|
| 82 |
Simulated temperature of a tungsten spot facing large plasma heat loads
|
Moritz, J.
|
|
|
41 |
C |
p.
|
artikel
|
| 83 |
Simulations of divertor designs that spatially separate power and particle exhaust using mid-leg divertor particle pumping
|
Yu, J.H.
|
|
|
41 |
C |
p.
|
artikel
|
| 84 |
Simulations of tungsten fuzz growth and erosion under He/Ar mixed plasma irradiation on LP-MIES
|
Yang, K.R.
|
|
|
41 |
C |
p.
|
artikel
|
| 85 |
Simulation study of the influence of the outer target geometry on tungsten contamination: Horizontal vs. vertical target
|
Ding, Hongxin
|
|
|
41 |
C |
p.
|
artikel
|
| 86 |
SOLEDGE3X integrated core-edge modelling of tungsten sources, migration, and radiation in WEST plasmas
|
Varadarajan, N.
|
|
|
41 |
C |
p.
|
artikel
|
| 87 |
SOLPS-ITER modeling of divertor detachment in MAST-U’s super-X double null configuration and comparison to experiment
|
Maurizio, R.
|
|
|
41 |
C |
p.
|
artikel
|
| 88 |
Strength prediction and optimization for microwave sintering of large-dimension lithium hydride ceramics: GA-BP-ANN modeling
|
Yan, Hongzhou
|
|
|
41 |
C |
p.
|
artikel
|
| 89 |
Study of deuterium reflection on tungsten material with lithium coating in EAST tokamak
|
Long, Qian
|
|
|
41 |
C |
p.
|
artikel
|
| 90 |
Study of spectral features and depth distributions of boron layers on tungsten substrates by ps-LIBS in a vacuum environment
|
Wu, Huace
|
|
|
41 |
C |
p.
|
artikel
|
| 91 |
Survey of tungsten gross erosion from main plasma facing components in WEST during a L-mode high fluence campaign
|
Fedorczak, N.
|
|
|
41 |
C |
p.
|
artikel
|
| 92 |
Systematic study of displacement threshold and the near-threshold primary radiation damage model
|
Chen, Shuyi
|
|
|
41 |
C |
p.
|
artikel
|
| 93 |
The dominant roles of “electron-density-mechanism” and “chemical-bonding-mechanism” for hydrogen in molybdenum and lithium
|
Han, Quan-Fu
|
|
|
41 |
C |
p.
|
artikel
|
| 94 |
The effect of CD4 injection on WD molecule sputtering at the divertor target in EAST
|
Zhang, Q.
|
|
|
41 |
C |
p.
|
artikel
|
| 95 |
The effect of D 2 partial pressure, deposition rate, and sample temperature on D retention in W codeposited layers
|
Patino, M.I.
|
|
|
41 |
C |
p.
|
artikel
|
| 96 |
The energetics and kinetics of H in δ-TiH2: Ab initio study
|
Wang, Tao
|
|
|
41 |
C |
p.
|
artikel
|
| 97 |
Theoretical investigation of structural, electronic, mechanical, surface work function and thermodynamic properties of La1-xMxB6 (M = Ba, Sr, Ca) compounds: Potential plasma grid materials in N-NBI system
|
Hu, Jun
|
|
|
41 |
C |
p.
|
artikel
|
| 98 |
Thermal and statistical analysis of the high-Z tungsten-based UFOs observed during the first deuterium high fluence campaign of the WEST tokamak
|
Gaspar, J.
|
|
|
41 |
C |
p.
|
artikel
|
| 99 |
Toroidal distribution of heat load on castellated plasma facing components for lower divertor target in EAST
|
Fu, Wenxue
|
|
|
41 |
C |
p.
|
artikel
|
| 100 |
Utilization of D2 molecular band emission for electron density measurement
|
Nishijima, D.
|
|
|
41 |
C |
p.
|
artikel
|
| 101 |
Validating reduced models for detachment onset and reattachment times on MAST-U
|
Henderson, S.S.
|
|
|
41 |
C |
p.
|
artikel
|
| 102 |
Wall conditions in WEST during operations with a new ITER grade, actively cooled divertor
|
Gallo, A.
|
|
|
41 |
C |
p.
|
artikel
|
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