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                             64 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Analytical approach for description of deuterium content in deuterium-beryllium co-deposited layers Krat, S.

26 C p.
artikel
2 A sensitivity analysis of numerical predictions for beryllium erosion and migration in ITER Romazanov, J.

26 C p.
artikel
3 Assessment of Scrape-Off Layer and divertor plasma conditions in JT-60SA with tungsten wall and nitrogen injection Rubino, G.

26 C p.
artikel
4 A study of the influence of plasma–molecule interactions on particle balance during detachment Verhaegh, Kevin

26 C p.
artikel
5 Atomistic study on helium-to-vacancy ratio of neutron irradiation induced helium bubbles during nucleation and growth in α-Fe Shi, Jingyi

26 C p.
artikel
6 Broadening of the power fall-off length in a high density, high confinement H-mode regime in ASDEX Upgrade Faitsch, M.

26 C p.
artikel
7 Determination of electron backscattering coefficient of beryllium by a high-precision Monte Carlo simulation Hussain, Abrar

26 C p.
artikel
8 Deuterium and helium outgassing following plasma discharges in WEST: Delayed D outgassing during D-to-He changeover experiments studied with threshold ionization mass spectrometry Bisson, R.

26 C p.
artikel
9 Developments on two lithium vapor-box linear test-stand experiments Schwartz, Jacob A.

26 C p.
artikel
10 3D modeling of boron transport in DIII-D L-mode wall conditioning experiments Effenberg, F.

26 C p.
artikel
11 EMC3-EIRENE modelling of the toroidally asymmetric heat flux distribution with neon impurity injection on EAST Liu, B.

26 C p.
artikel
12 Evaluation of hydrogen retention behavior in tungsten exposed to hydrogen plasma in QUEST Koike, Ayaka

26 C p.
artikel
13 Evaluation of irradiation hardening in ODS-Cu and non ODS-Cu by nanoindentation hardness test and micro-pillar compression test after self-ion irradiation Liu, Yuchen

26 C p.
artikel
14 Experimental observation of heat flux mitigation during divertor detachment in the DIII-D small angle slot divertor Ren, J.

26 C p.
artikel
15 Experimental observations and modelling of radiation asymmetries during N2 seeding in LHD Peterson, B.J.

26 C p.
artikel
16 First measurements of aluminum erosion by neutral particles on EAST tokamak Mu, L.

26 C p.
artikel
17 Global distribution of tritium in JET with the ITER-like wall Lee, S.E.

26 C p.
artikel
18 High-accuracy compliance correction for nonlinear mechanical testing: Improving Small Punch Test characterization Sánchez-Ávila, David

26 C p.
artikel
19 Hydrogen content in divertor baffle tiles in Wendelstein 7-X Oelmann, Jannis

26 C p.
artikel
20 Identification of forbidden emission lines from highly ionized tungsten ions in VUV wavelength range in LHD for ITER edge plasma diagnostics Oishi, Tetsutarou

26 C p.
artikel
21 Impact of blanket material and configuration on the size of a tokamak fusion reactor Hong, Bong Guen

26 C p.
artikel
22 Impact of ion temperature anisotropy on 2D edge-plasma transport Zhao, M.

26 C p.
artikel
23 Impact of lithium wall conditioning and wave-frequency on high density lower hybrid current drive experiment on EAST Baek, S.G.

26 C p.
artikel
24 Impact of plasma-wall interaction and exhaust on the EU-DEMO design Maviglia, F.

26 C p.
artikel
25 Impact of the new TCV baffled divertor upgrade on pedestal structure and performance Sheikh, U.A.

26 C p.
artikel
26 Impacts of impurity flux on erosion and deposition of carbon/tungsten rough surfaces Dai, S.Y.

26 C p.
artikel
27 Influence of nitrogen on deuterium retention in tungsten under sequential and simultaneous irradiation Goodland, M.E.

26 C p.
artikel
28 Infrared thermography in metallic environments of WEST and ASDEX Upgrade Aumeunier, M-H.

26 C p.
artikel
29 In situ method for studying stresses in a pulse-heated tungsten plate based on measurements of surface curvature Cherepanov, D.E.

26 C p.
artikel
30 Interaction between filaments and ICRF in the plasma edge Zhang, W.

26 C p.
artikel
31 Interpretative SOL modeling throughout multiple ELM cycles in DIII-D Nelson, A.O.

26 C p.
artikel
32 Investigation of radial distribution of atomic hydrogen flux to the plasma facing components in steady state discharges in QUEST tokamak Kuzmin, A.

26 C p.
artikel
33 Investigation of the distribution of remaining tritium in divertor in LHD Masuzaki, S.

26 C p.
artikel
34 Investigation of the impact of flux expansion on tungsten content and radiation in JET-ILW Minucci, S.

26 C p.
artikel
35 Kinetic model of the COMPASS tokamak SOL Tskhakaya, D.

26 C p.
artikel
36 Localized Nb clusters in U-Nb liquid alloys: An ab initio molecular dynamics study Shi, Yongpeng

26 C p.
artikel
37 Measurement of the 2D emission profiles of hydrogen and impurity ions in the TCV divertor Perek, A.

26 C p.
artikel
38 Microstructure-specific hardening of ferritic-martensitic steels pre and post 15 dpa neutron irradiation at 330 °C: A dislocation dynamics study Mahler, Michael

26 C p.
artikel
39 Modeling of liquid lithium flow in porous plasma facing material Khodak, Andrei

26 C p.
artikel
40 Modeling snowflake divertors in MAST-U tokamak using UEDGE code Khrabry, A.I.

26 C p.
artikel
41 Modelling of hydrogen atoms reflection from an annealed tungsten fuzzy surfaces Liu, D.H.

26 C p.
artikel
42 Neutron irradiated tungsten bulk defect characterization by positron annihilation spectroscopy Taylor, Chase N.

26 C p.
artikel
43 Nonlinear simulation of edge localized mode with pressure profile modified by pellet injection through a BOUT++ three-field MHD model Li, Mao

26 C p.
artikel
44 Numerical simulation study of impurity B transport during real-time B powder injection in EAST Peng, Lei

26 C p.
artikel
45 Perspective of analogy between heat loads and impurity production in L-mode discharges with ICRH in WEST Urbanczyk, G.

26 C p.
artikel
46 Preliminary analysis of alternative divertors for DEMO Militello, F.

26 C p.
artikel
47 Progress of tungsten spectral modeling for ITER edge plasma diagnostics based on tungsten spectroscopy in LHD Murakami, I.

26 C p.
artikel
48 Proton and Au-ion irradiation induced damage and hardening in ferritic/martensitic steel Shi, Ke

26 C p.
artikel
49 Quantifying erosion and retention of silicon carbide due to D plasma irradiation in a high-flux linear plasma device Sinclair, G.

26 C p.
artikel
50 Radiation response on the Nb/MgO interface with different interface angles Du, J.L.

26 C p.
artikel
51 Real time monitoring of material erosion and deposition for the first wall using quartz crystal microbalance in EAST Zhang, Y.

26 C p.
artikel
52 Role of zirconium in neodymium-dopants interactions within uranium-based metallic fuels Khanal, Rabi

26 C p.
artikel
53 Scoping the characteristics and benefits of a connected double-null configuration for power exhaust in EU-DEMO Aho-Mantila, L.

26 C p.
artikel
54 Simplified approach for ductile fracture mechanics SSTT and its application to Eurofer97 Mahler, Michael

26 C p.
artikel
55 Simulation studies of divertor detachment and critical power exhaust parameters for Japanese DEMO design Asakura, N.

26 C p.
artikel
56 SOLPS-ITER drift modelling of ITER burning plasmas with narrow near-SOL heat flux channels Veselova, Irina

26 C p.
artikel
57 Stability of nanograins and nanoparticles in La-doped nanocrystalline steel irradiated with Fe ions Liu, Haocheng

26 C p.
artikel
58 Study of detachment in future ASDEX Upgrade alternative divertor configurations by means of EMC3-EIRENE Lunt, T.

26 C p.
artikel
59 Sustained radiative divertor in high-performance grassy-ELM regime with metal wall towards long-pulse operation in EAST Li, K.D.

26 C p.
artikel
60 Synthesis of simulated fuels containing CsI under gas-tight condition Liu, J.Z.

26 C p.
artikel
61 The interactions between nitrogen oxides and α-uranium surface Liu, Guangdong

26 C p.
artikel
62 Toroidal flow measurements of impurity ions in QUEST ECH plasmas using multiple viewing chords emission spectroscopy Yoneda, N.

26 C p.
artikel
63 Towards assessment of plasma edge transport in Neon seeded plasmas in disconnected double null configuration in EAST with SOLPS-ITER Boeyaert, D.

26 C p.
artikel
64 Use of the small punch test for the estimation of ductile-to-brittle transition temperature shift of irradiated steels Altstadt, E.

26 C p.
artikel
                             64 gevonden resultaten
 
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