nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
Accumulated 2-D neutron flux distribution during KSTAR operation
|
Kwak, Jong-Gu |
|
2018 |
136 |
PA |
p. 777-781 |
artikel |
2 |
Activation analysis of coolant in a water-cooled loop of China fusion engineering test reactor
|
Guo, Qingyang |
|
2018 |
136 |
PA |
p. 694-698 |
artikel |
3 |
Activity inventories and decay heat generation of the Test Cell facility of IFMIF-DONES
|
Stankunas, Gediminas |
|
2018 |
136 |
PA |
p. 617-622 |
artikel |
4 |
Advanced high-temperature superconducting magnet for fusion reactors: Segment fabrication and joint technique
|
Ito, Satoshi |
|
2018 |
136 |
PA |
p. 239-246 |
artikel |
5 |
An action plan of Japan toward development of demo reactor
|
Okano, Kunihiko |
|
2018 |
136 |
PA |
p. 183-189 |
artikel |
6 |
Analyses of the quench tank configuration for DONES liquid-lithium target system
|
Gordeev, Sergej |
|
2018 |
136 |
PA |
p. 330-334 |
artikel |
7 |
Analysis of the EU-DEMO fuel cycle elements: Intrinsic impact of technology choices
|
Hörstensmeyer, Yannick Nicolas |
|
2018 |
136 |
PA |
p. 314-318 |
artikel |
8 |
An FEM-BEM method for halo current problem and its application to HL-2M Tokamak
|
Li, Xudong |
|
2018 |
136 |
PA |
p. 667-673 |
artikel |
9 |
Assessment and optimization of MCNP memory management for detailed geometry of nuclear fusion facilities
|
Alguacil, J. |
|
2018 |
136 |
PA |
p. 386-389 |
artikel |
10 |
Assessment of the JT-60SA divertor cryopump performance
|
Luo, Xueli |
|
2018 |
136 |
PA |
p. 467-471 |
artikel |
11 |
A study on influence of magnetic field on fracture properties of China low activation martensitic steel
|
Xie, Zheng |
|
2018 |
136 |
PA |
p. 706-711 |
artikel |
12 |
A tungsten guard limiter for EAST 4.6 GHz lower hybrid waveguide antennas
|
Zhang, Liangliang |
|
2018 |
136 |
PA |
p. 447-453 |
artikel |
13 |
Availability improvement of ITER blanket remote handling system
|
Maruyama, Takahito |
|
2018 |
136 |
PA |
p. 390-393 |
artikel |
14 |
Calibration experiment and the neutronics analyses on the LHD neutron flux monitors for the deuterium plasma experiment
|
Nishitani, Takeo |
|
2018 |
136 |
PA |
p. 210-214 |
artikel |
15 |
Characterisation of neutron generators and monitoring detectors for the in-vessel calibration of JET
|
Ghani, Z. |
|
2018 |
136 |
PA |
p. 233-238 |
artikel |
16 |
Characterization of vanadium beryllide pebble bed for the Japan DEMO blanket application
|
Nakamichi, Masaru |
|
2018 |
136 |
PA |
p. 125-127 |
artikel |
17 |
Compatibility test of common electronics with gaseous tritium
|
Priester, Florian |
|
2018 |
136 |
PA |
p. 608-611 |
artikel |
18 |
Conceptual design and verification of long-distance laser-probe system for Li target diagnostics of intense fusion neutron source
|
Kondo, Hiroo |
|
2018 |
136 |
PA |
p. 24-28 |
artikel |
19 |
Conceptual design of HCCR-TBM diagnostics
|
Kim, Chang-Shuk |
|
2018 |
136 |
PA |
p. 717-721 |
artikel |
20 |
Conceptual designs of PHTS, ESS and PCS for DEMO BoP with helium cooled BB concept
|
Bubelis, Evaldas |
|
2018 |
136 |
PA |
p. 367-371 |
artikel |
21 |
Control of dehumidification using polymer permeable membrane and its application to tritium removal system design
|
Tanaka, Masahiro |
|
2018 |
136 |
PA |
p. 141-145 |
artikel |
22 |
Damping effect on the ITER vacuum vessel displacements during slow downward locked and rotating asymmetric vertical displacement events
|
Testoni, Pietro |
|
2018 |
136 |
PA |
p. 265-269 |
artikel |
23 |
Definition of the Q-PETE experiment for investigation of hydrogen isotopes permeation through the metal structures of a DEMO HCPB breeder zone
|
Klimenko, Dmitry |
|
2018 |
136 |
PA |
p. 563-568 |
artikel |
24 |
DEMO design activity in Europe: Progress and updates
|
Federici, G. |
|
2018 |
136 |
PA |
p. 729-741 |
artikel |
25 |
Design, manufacturing and installation of the JT-60SA vacuum vessel gravity support
|
Asano, Shiro |
|
2018 |
136 |
PA |
p. 661-666 |
artikel |
26 |
Design of port structure between vacuum vessel and cryostat in JT-60SA
|
Nakamura, Shigetoshi |
|
2018 |
136 |
PA |
p. 135-140 |
artikel |
27 |
Design progress of ITER blanket remote handling system towards manufacturing
|
Noguchi, Y. |
|
2018 |
136 |
PA |
p. 722-728 |
artikel |
28 |
Design status of the double Closure Plate Sub-Plate concept for the ITER Electron Cyclotron Upper Launcher
|
Mas Sánchez, Avelino |
|
2018 |
136 |
PA |
p. 503-508 |
artikel |
29 |
Development of an advanced magnetic equilibrium model for fusion reactor system codes
|
Franza, F. |
|
2018 |
136 |
PA |
p. 309-313 |
artikel |
30 |
Development of a simulation method for evaluating Marangoni convection with free surface for tungsten divertor
|
Hamaguchi, Kohei |
|
2018 |
136 |
PA |
p. 270-275 |
artikel |
31 |
Development of calorimeter system for conceptual study of CuspDEC divertor
|
Ichimura, Kazuya |
|
2018 |
136 |
PA |
p. 381-385 |
artikel |
32 |
Development of combined temperature – Electric potential sensors
|
Bühler, L. |
|
2018 |
136 |
PA |
p. 7-11 |
artikel |
33 |
Development of helium coolant DEMO first wall model for SYCOMORE system code based on HCLL concept
|
Spagnuolo, Gandolfo Alessandro |
|
2018 |
136 |
PA |
p. 488-492 |
artikel |
34 |
Development of tungsten divertor components for ITER in Japan
|
Ezato, K. |
|
2018 |
136 |
PA |
p. 683-689 |
artikel |
35 |
3D modelling of tungsten fuzz growth under the bombardment of helium plasma
|
Shi, Quan |
|
2018 |
136 |
PA |
p. 554-557 |
artikel |
36 |
Dust generation in tokamaks: Overview of beryllium and tungsten dust characterisation in JET with the ITER-like wall
|
Rubel, M. |
|
2018 |
136 |
PA |
p. 579-586 |
artikel |
37 |
Editorial Board
|
|
|
2018 |
136 |
PA |
p. ii |
artikel |
38 |
Effects of baking in deuterium atmosphere on tritium removal from tungsten
|
Nobuta, Yuji |
|
2018 |
136 |
PA |
p. 674-677 |
artikel |
39 |
Effects of shot-peening on permeation and retention behaviors of hydrogen in alpha iron
|
Otsuka, Teppei |
|
2018 |
136 |
PA |
p. 509-512 |
artikel |
40 |
ENDF/B-VIIIβ4 benchmark test with iron and concrete shielding experiments using 40 and 65MeV neutrons at QST/TIARA
|
Kwon, Saerom |
|
2018 |
136 |
PA |
p. 2-6 |
artikel |
41 |
Enhancement of cooling performance of a helium-cooled divertor through the addition of rib structures on the jet-impingement area
|
Lim, Joon-Soo |
|
2018 |
136 |
PA |
p. 655-660 |
artikel |
42 |
Evaluation of Li mass loss from Li2TiO3 with excess Li pebbles in water vapor atmosphere
|
Katayama, Kazunari |
|
2018 |
136 |
PA |
p. 362-366 |
artikel |
43 |
Experimental and numerical studies of helium-cooled modular divertors with multiple jets
|
Zhao, Bailey |
|
2018 |
136 |
PA |
p. 67-71 |
artikel |
44 |
Experimental campaign on pressure wave propagation in LLE
|
Venturini, A. |
|
2018 |
136 |
PA |
p. 809-814 |
artikel |
45 |
Experimental evaluation of tritium oxidation efficiency in the room temperature recombiner
|
Iwai, Yasunori |
|
2018 |
136 |
PA |
p. 120-124 |
artikel |
46 |
Experimental study on the lithium film flow in the spanwise magnetic field
|
Liu, Bai-Qi |
|
2018 |
136 |
PA |
p. 522-526 |
artikel |
47 |
Experimental validation of thermo-mechanical simulations of ITER diagnostic pressure gauges
|
Arkhipov, Alexey |
|
2018 |
136 |
PA |
p. 398-402 |
artikel |
48 |
Exploring complex high heat flux geometries for fusion applications enabled by additive manufacturing
|
Hancock, David |
|
2018 |
136 |
PA |
p. 454-460 |
artikel |
49 |
Fabrication feasibility studies for first wall of Indian LLCB TBM
|
Sam, Shiju |
|
2018 |
136 |
PA |
p. 771-776 |
artikel |
50 |
Fabrication of tungsten and carbon clad plates by sinter bonding methods for divertor system characterization
|
Kishimoto, Hirotatsu |
|
2018 |
136 |
PA |
p. 116-119 |
artikel |
51 |
Fabrication technology development and characterization of tritium permeation barriers by a liquid phase method
|
Chikada, Takumi |
|
2018 |
136 |
PA |
p. 215-218 |
artikel |
52 |
FEM and thermal fatigue testing comparison of ITER-like divertor PFUs mock-ups for DEMO
|
Crescenzi, F. |
|
2018 |
136 |
PA |
p. 558-562 |
artikel |
53 |
First Results from the Soft X-ray Pulse Height Analysis System on Wendelstein 7-X Stellarator
|
Kubkowska, Monika |
|
2018 |
136 |
PA |
p. 58-62 |
artikel |
54 |
Flow analysis and test for ITER thermal shield components
|
Nam, Kwanwoo |
|
2018 |
136 |
PA |
p. 752-758 |
artikel |
55 |
Heat transfer performance of an energy-saving heat removal device with uni-directional porous copper for divertor cooling
|
Takai, Kio |
|
2018 |
136 |
PA |
p. 518-521 |
artikel |
56 |
Hybrid Monte Carlo approach for accurate and efficient shutdown dose rate calculation
|
Lu, Peng |
|
2018 |
136 |
PA |
p. 498-502 |
artikel |
57 |
Hydrogen permeation through flinabe including Ti powder
|
Yamashita, Jun |
|
2018 |
136 |
PA |
p. 173-177 |
artikel |
58 |
Ignition studies of D-3He spherical tokamak reactor
|
Mitarai, Osamu |
|
2018 |
136 |
PA |
p. 82-86 |
artikel |
59 |
Influence of modified neutron emission spectrum on tritium production performance in blanket systems with NBI-heated deuterium plasma
|
Urakawa, Tomoki |
|
2018 |
136 |
PA |
p. 678-682 |
artikel |
60 |
Initial layout of DEMO buildings and configuration of the main plant systems
|
Gliss, Curt |
|
2018 |
136 |
PA |
p. 534-539 |
artikel |
61 |
Initial result of neutron energy spectrum reconstruction using multi-foil activation method in KSTAR
|
Jo, Jungmin |
|
2018 |
136 |
PA |
p. 793-796 |
artikel |
62 |
Innovative joining of Pd-Ag permeator tubes
|
Moriani, Andrea |
|
2018 |
136 |
PA |
p. 426-430 |
artikel |
63 |
In-situ evaluation of radiation induced optical degradation of candidate scintillator materials for ITER’s gamma and neutron detectors
|
García-Cortés, Isabel |
|
2018 |
136 |
PA |
p. 493-497 |
artikel |
64 |
Inspection of delamination defect in first wall with a flexible EMAT-scanning system
|
Pei, Cuixiang |
|
2018 |
136 |
PA |
p. 549-553 |
artikel |
65 |
Investigation of edge impurity transport derived from the first wall on EAST with EMC3-EIRENE modelling
|
Xie, Tian |
|
2018 |
136 |
PA |
p. 699-705 |
artikel |
66 |
Investigation of material homogenisation on the nuclear heating estimates of the electron cyclotron-heating upper launcher blanket shield module
|
Weinhorst, Bastian |
|
2018 |
136 |
PA |
p. 481-487 |
artikel |
67 |
Investigation of technical gaps between DEMO blanket and HCCR TBM
|
Cho, Seungyon |
|
2018 |
136 |
PA |
p. 190-198 |
artikel |
68 |
ITER ECRH Upper Launcher diamond window – Qualification and testing of a Protection Important Component
|
Schreck, Sabine |
|
2018 |
136 |
PA |
p. 472-476 |
artikel |
69 |
Large-scale behavior of sandwich-like FCI components within the EU-DCLL operational conditions
|
Fernández-Berceruelo, I. |
|
2018 |
136 |
PA |
p. 633-638 |
artikel |
70 |
Laser cutting and welding tools for use in-bore on EU-DEMO service pipes
|
Keogh, K. |
|
2018 |
136 |
PA |
p. 461-466 |
artikel |
71 |
Laser welding of fusion relevant steels for the European DEMO
|
Kirk, Simon |
|
2018 |
136 |
PA |
p. 612-616 |
artikel |
72 |
Latest achievements of the negative ion beam test facility ELISE
|
Heinemann, B. |
|
2018 |
136 |
PA |
p. 569-574 |
artikel |
73 |
Liquid PbLi atomization in vacuum for tritium and heat recovery
|
Okino, Fumito |
|
2018 |
136 |
PA |
p. 63-66 |
artikel |
74 |
Lithium isotope separation using displacement chromatography by cation exchange resin with high degree of cross-linkage
|
Putra, Andri Rahma |
|
2018 |
136 |
PA |
p. 377-380 |
artikel |
75 |
MASCOT 6: Achieving high dexterity tele-manipulation with a modern architectural design for fusion remote maintenance
|
Skilton, Robert |
|
2018 |
136 |
PA |
p. 575-578 |
artikel |
76 |
Materials engineering and design for fusion—Towards DEMO design criteria
|
Gorley, Michael |
|
2018 |
136 |
PA |
p. 298-303 |
artikel |
77 |
Mechanical properties and thermal stability of carbide dispersion strengthened CLF-1 steel
|
Yang, Shuang |
|
2018 |
136 |
PA |
p. 442-446 |
artikel |
78 |
Methodology to identify appropriate options to manage tritiated waste
|
Decanis, Christelle |
|
2018 |
136 |
PA |
p. 276-281 |
artikel |
79 |
MHD pressure drop measurement of PbLi flow in double-bended pipe
|
Nakamura, Shoki |
|
2018 |
136 |
PA |
p. 17-23 |
artikel |
80 |
Modeling of fuel retention and hydrogen-isotope exchange removal from the pre-damaged tungsten material
|
Wang, Zhenhou |
|
2018 |
136 |
PA |
p. 372-376 |
artikel |
81 |
Neutronics analyses for a stellarator power reactor based on the HELIAS concept
|
Häußler, André |
|
2018 |
136 |
PA |
p. 345-349 |
artikel |
82 |
New high performance computing software for multiphysics simulations of fusion reactors
|
Gutierrez-Milla, Albert |
|
2018 |
136 |
PA |
p. 639-644 |
artikel |
83 |
Nozzle-to-target distance effect on the cooling performances of a jet-impingement helium-cooled divertor
|
Lee, Namkyu |
|
2018 |
136 |
PA |
p. 803-808 |
artikel |
84 |
Nuclear analysis of the ITER In-Vessel viewing system
|
Travleev, Anton |
|
2018 |
136 |
PA |
p. 247-251 |
artikel |
85 |
Nuclear and thermal feasibility of lithium-loaded high temperature gas-cooled reactor for tritium production for fusion reactors
|
Goto, Minoru |
|
2018 |
136 |
PA |
p. 357-361 |
artikel |
86 |
Numerical analyses for conceptual design of an irradiation PbLi capsule for testing of protective coatings for the European DEMO breeding blanket project
|
Vála, Ladislav |
|
2018 |
136 |
PA |
p. 797-802 |
artikel |
87 |
Numerical and experimental study of coolant water flow in ITER divertor outer vertical target
|
Seki, Yohji |
|
2018 |
136 |
PA |
p. 420-425 |
artikel |
88 |
Numerical investigation for lithium isotope effect in ionic superconductor
|
Kobayashi, Keita |
|
2018 |
136 |
PA |
p. 205-209 |
artikel |
89 |
Numerical simulation and experimental research on temperature and stress fields in TIG welding for plate of RAFM steel
|
Liu, Sumei |
|
2018 |
136 |
PA |
p. 690-693 |
artikel |
90 |
Operational characteristics of the superconducting high flux plasma generator Magnum-PSI
|
van de Pol, M.J. |
|
2018 |
136 |
PA |
p. 597-601 |
artikel |
91 |
Operational domain of Proto-MPEX
|
Rapp, Juergen |
|
2018 |
136 |
PA |
p. 712-716 |
artikel |
92 |
Optimal scheduling model to minimize tritium inventory level in fuel cycle of tritium plant
|
Lee, Suh-Young |
|
2018 |
136 |
PA |
p. 747-751 |
artikel |
93 |
Overview of fatigue life assessment of baffles in Wendelstein 7-X
|
Fellinger, Joris |
|
2018 |
136 |
PA |
p. 292-297 |
artikel |
94 |
Overview of manufacturing technologies under development in Russia for ITER plasma facing components
|
Giniyatulin, R.N. |
|
2018 |
136 |
PA |
p. 527-533 |
artikel |
95 |
Overview of the current status of IFMIF-DONES test cell biological shielding design
|
Tian, Kuo |
|
2018 |
136 |
PA |
p. 628-632 |
artikel |
96 |
Overview of the electron cyclotron emission measurements on EAST
|
Liu, Yong |
|
2018 |
136 |
PA |
p. 72-75 |
artikel |
97 |
Overview of the TRANSAT (TRANSversal Actions for Tritium) project
|
Liger, Karine |
|
2018 |
136 |
PA |
p. 168-172 |
artikel |
98 |
Overview over DEMO design integration challenges and their impact on component design concepts
|
Bachmann, C. |
|
2018 |
136 |
PA |
p. 87-95 |
artikel |
99 |
Performance improvement due to additional collectors in a secondary electron direct energy converter simulator
|
Nakamoto, Satoshi |
|
2018 |
136 |
PA |
p. 157-161 |
artikel |
100 |
Plasma-wall interaction on the divertor tiles of JET ITER-like wall from the viewpoint of micro/nanoscopic observations
|
Tokitani, M. |
|
2018 |
136 |
PA |
p. 199-204 |
artikel |
101 |
Preface for fusion engineering and design special issue for ISFNT-13
|
Cho, Seungyon |
|
2018 |
136 |
PA |
p. 1 |
artikel |
102 |
Preparation and characterization of Er2O3-ZrO2 multi-layer coating for tritium permeation barrier by metal organic decomposition
|
Mochizuki, Jumpei |
|
2018 |
136 |
PA |
p. 219-222 |
artikel |
103 |
Production of Be-Ti and Be-Zr rods by extrusion and their characterization
|
Kurinskiy, Petr |
|
2018 |
136 |
PA |
p. 49-52 |
artikel |
104 |
Progress in EU Breeding Blanket design and integration
|
Cismondi, F. |
|
2018 |
136 |
PA |
p. 782-792 |
artikel |
105 |
Proposal for Combined Electrolysis and Catalytic Exchange System (CECE) development within the Pilot Plant
|
Bornea, Anisia |
|
2018 |
136 |
PA |
p. 645-649 |
artikel |
106 |
Proposal of fluid stirring by multi-layered trenches for liquid metal divertor
|
Kawamoto, Makoto |
|
2018 |
136 |
PA |
p. 415-419 |
artikel |
107 |
Qualification and post-mortem investigation of actively cooled tungsten flat-tile mock-ups for WEST divertor
|
Missirlian, M. |
|
2018 |
136 |
PA |
p. 403-409 |
artikel |
108 |
Radiation safety study for the beam commissioning of IFMIF/EVEDA LIPAc RFQ in Rokkasho
|
Kondo, Keitaro |
|
2018 |
136 |
PA |
p. 252-257 |
artikel |
109 |
Radiation shielding calculations for a 3D ITER benchmark model using TRIPOLI-4® Monte Carlo code
|
Lee, Yi-Kang |
|
2018 |
136 |
PA |
p. 602-607 |
artikel |
110 |
Removing W-contaminants in helium and neon RF plasma to maintain the optical performance of the ITER UWAVS first mirror
|
Ushakov, Andrey |
|
2018 |
136 |
PA |
p. 431-437 |
artikel |
111 |
Retention and permeation properties of deuterium in tungsten under irradiation of the D–He mixture plasma
|
Hayashi, Tatsuya |
|
2018 |
136 |
PA |
p. 545-548 |
artikel |
112 |
Sacrificial effect of titanium powder on the corrosion by hydrogen fluoride in LiF-NaF-KF
|
Yamazaki, Gaku |
|
2018 |
136 |
PA |
p. 394-397 |
artikel |
113 |
Safety provisions for the ITER facility
|
Rosanvallon, Sandrine |
|
2018 |
136 |
PA |
p. 540-544 |
artikel |
114 |
Shutdown dose rate mitigation in the ITER upper ports
|
Kolšek, Aljaž |
|
2018 |
136 |
PA |
p. 228-232 |
artikel |
115 |
Simulations and pre-experiment uncertainty analyses for a hydrogen diffusion experiment using a “two side purged membrane” setup
|
Arbeiter, Frederik |
|
2018 |
136 |
PA |
p. 287-291 |
artikel |
116 |
Simulation study on a merging core fueling technique for an advanced fuel fusion spherical tokamak reactor
|
Koike, Shintato |
|
2018 |
136 |
PA |
p. 111-115 |
artikel |
117 |
Solid state diffusion bonding of doped tungsten alloys with different thermo-mechanical properties
|
Nogami, Shuhei |
|
2018 |
136 |
PA |
p. 76-81 |
artikel |
118 |
Spectroscopic study of hydrogen reflection at modified tungsten surface
|
Doi, Kenta |
|
2018 |
136 |
PA |
p. 100-105 |
artikel |
119 |
Status and future developments of R&D on fiber optics current sensor for ITER
|
Gusarov, Andrei |
|
2018 |
136 |
PA |
p. 477-480 |
artikel |
120 |
Structural assessment of the HCPB breeding blanket segments in the EU DEMO reactor under normal operation and a central plasma disruption
|
Zeile, Christian |
|
2018 |
136 |
PA |
p. 335-339 |
artikel |
121 |
Study of the optimal configuration for a Gas Electron Multiplier aimed at plasma impurity radiation monitoring
|
Chernyshova, Maryna |
|
2018 |
136 |
PA |
p. 592-596 |
artikel |
122 |
Study on chemical kinetics of HTO + H2 → H2O + HT for design of tritium breeding blanket
|
Furudate, Michiko Ahn |
|
2018 |
136 |
PA |
p. 438-441 |
artikel |
123 |
Study on lithium rod test module and irradiation method for tritium production using high temperature gas-cooled reactor
|
Koga, Yuki |
|
2018 |
136 |
PA |
p. 587-591 |
artikel |
124 |
Study on measurement of the flow velocity of liquid lithium jet using MHD effect for IFMIF
|
Okita, Takafumi |
|
2018 |
136 |
PA |
p. 178-182 |
artikel |
125 |
Study on melting and solidification behaviors of tungsten loaded by high heat flux for divertor in tokamak fusion reactor
|
Hoashi, Eiji |
|
2018 |
136 |
PA |
p. 350-356 |
artikel |
126 |
Study on the heat exchange efficiency of ITER GS thermal anchor
|
Sun, Zhenchao |
|
2018 |
136 |
PA |
p. 96-99 |
artikel |
127 |
System design and engineering for baking of the KTM vacuum vessel
|
Tanchuk, Victor |
|
2018 |
136 |
PA |
p. 759-765 |
artikel |
128 |
Systems engineering perspective to the integration of the heating and current drive system in the EU DEMO: Analysis of requirements and functions
|
Grossetti, Giovanni |
|
2018 |
136 |
PA |
p. 53-57 |
artikel |
129 |
Technology developments for a beam source of an NNBI system for DEMO
|
Fantz, U. |
|
2018 |
136 |
PA |
p. 340-344 |
artikel |
130 |
Testing of tritium breeder blanket activation foil spectrometer during JET operations
|
Colling, Bethany |
|
2018 |
136 |
PA |
p. 258-264 |
artikel |
131 |
The effect of wall flow velocity on compatibility of high-purity SiC materials with liquid Pb-Li alloy by rotating disc testing for 3000 h up to 900 °C
|
Park, ChangHo |
|
2018 |
136 |
PA |
p. 623-627 |
artikel |
132 |
The impact of neon-seeding location on the divertor plasma in EAST
|
Liu, Daoyuan |
|
2018 |
136 |
PA |
p. 324-329 |
artikel |
133 |
The ITER tokamak neutronics reference model C-Model
|
Leichtle, Dieter |
|
2018 |
136 |
PA |
p. 742-746 |
artikel |
134 |
The magnet system of Wendelstein 7-X stellarator in operation
|
Risse, Konrad |
|
2018 |
136 |
PA |
p. 12-16 |
artikel |
135 |
Thermal and flow analyses on the cartridge-type blanket CARDISTRY-B for the helical fusion reactor FFHR-c1
|
Murase, Takanori |
|
2018 |
136 |
PA |
p. 106-110 |
artikel |
136 |
Thermal hydraulic analysis of water cooled blanket under transient condition
|
Cui, Qinglan |
|
2018 |
136 |
PA |
p. 151-156 |
artikel |
137 |
Thermal mechanical analyses of the mm-wave miter bend for the ITER electron cyclotron upper launcher first confinement system
|
Santos Silva, Phillip |
|
2018 |
136 |
PA |
p. 650-654 |
artikel |
138 |
Thermal mechanical characteristics of blanket first walls with different cooling channel shapes
|
Gwon, Hyoseong |
|
2018 |
136 |
PA |
p. 146-150 |
artikel |
139 |
Thermal mixing enhancement of liquid metal MHD free-surface flow by optimizing vortex generator arrays
|
Kusumi, Koji |
|
2018 |
136 |
PA |
p. 223-227 |
artikel |
140 |
Thermo-mechanical analysis of an ITER ECH&CD Upper Launcher mirror
|
Vagnoni, Matteo |
|
2018 |
136 |
PA |
p. 766-770 |
artikel |
141 |
The role of nuclear data for fusion nuclear technology
|
Fischer, U. |
|
2018 |
136 |
PA |
p. 162-167 |
artikel |
142 |
TOKES simulations to compare gas and pellet injection for disruption mitigation in ITER
|
Pestchanyi, S. |
|
2018 |
136 |
PA |
p. 29-33 |
artikel |
143 |
Transient thermal analysis and structural assessment of an ex-vessel LOCA event on the EU DEMO HCPB breeding blanket and the attachment system
|
Zhou, Guangming |
|
2018 |
136 |
PA |
p. 34-41 |
artikel |
144 |
Tritium breeding performance of a DEMO based on the Double Null divertor configuration
|
Pereslavtsev, Pavel |
|
2018 |
136 |
PA |
p. 282-286 |
artikel |
145 |
Tritium oxidation test by platinum-alumina catalyst under moisture and hydrocarbons atmosphere
|
Edao, Yuki |
|
2018 |
136 |
PA |
p. 319-323 |
artikel |
146 |
Tritium technologies and transport modelling: main outcomes from the European TBM Project
|
Ricapito, I. |
|
2018 |
136 |
PA |
p. 128-134 |
artikel |
147 |
Upgrades of edge, divertor and scrape-off layer diagnostics of W7‐X for OP1.2
|
Hathiramani, D. |
|
2018 |
136 |
PA |
p. 304-308 |
artikel |
148 |
Validation of miniature test specimens for post-irradiation thermal diffusivity measurement
|
Akiyoshi, Masafumi |
|
2018 |
136 |
PA |
p. 513-517 |
artikel |
149 |
Wall protection strategies for DEMO plasma transients
|
Maviglia, F. |
|
2018 |
136 |
PA |
p. 410-414 |
artikel |
150 |
Waste assessment of European DEMO fusion reactor designs
|
Gilbert, M.R. |
|
2018 |
136 |
PA |
p. 42-48 |
artikel |