| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A continuously pulsed Reversed Field Pinch core for an ohmically heated hybrid reactor
|
Piovan, R.
|
|
2018
|
136 |
PB |
p. 1489-1493
|
artikel
|
| 2 |
Activation material selection for multiple foil activation detectors in JET TT campaign
|
Lengar, Igor
|
|
2018
|
136 |
PB |
p. 988-992
|
artikel
|
| 3 |
Advanced manufacturing—A transformative enabling capability for fusion
|
Nygren, Richard E.
|
|
2018
|
136 |
PB |
p. 1007-1011
|
artikel
|
| 4 |
Analysis liquid lithium corrosion resistance of Er2O3 coating revealed by LIBS technique
|
Li, Ying
|
|
2018
|
136 |
PB |
p. 1640-1646
|
artikel
|
| 5 |
Analysis of EM loads on DEMO WCLL breeding blanket during VDE-up
|
Maione, Ivan A.
|
|
2018
|
136 |
PB |
p. 1523-1528
|
artikel
|
| 6 |
Analysis of test blanket module attachments under electromagnetic loads by using a dynamic amplification factor envelope
|
Muñoz, Raúl
|
|
2018
|
136 |
PB |
p. 1247-1251
|
artikel
|
| 7 |
Analysis of the optimum impurity mix for the EU DEMO scenario
|
Ivanova-Stanik, Irena
|
|
2018
|
136 |
PB |
p. 1313-1316
|
artikel
|
| 8 |
Application of laser induced breakdown spectroscopy for fast depth profiling analysis of type 316 stainless steel parts corroded by liquid lithium
|
Ke, Chuan
|
|
2018
|
136 |
PB |
p. 1647-1652
|
artikel
|
| 9 |
Application of the mesh adaptation technique to effective heat capacity method for melting simulation of the first wall in breeding blanket under high heat flux condition
|
Choe, Hee Su
|
|
2018
|
136 |
PB |
p. 891-896
|
artikel
|
| 10 |
A preliminary assessment of the vacuum performance in the beamline during IFMIF-DONES operation
|
Hauer, V.
|
|
2018
|
136 |
PB |
p. 1063-1067
|
artikel
|
| 11 |
Assessment of activated corrosion products for the DEMO WCLL
|
Di Pace, Luigi
|
|
2018
|
136 |
PB |
p. 1168-1172
|
artikel
|
| 12 |
Assessment of mixed neutron and photon radiation ratios using a tissue equivalent proportional counter on KSTAR
|
Lee, Y.S.
|
|
2018
|
136 |
PB |
p. 1112-1116
|
artikel
|
| 13 |
BB LOCA analysis for the reference design of the EU DEMO HCPB blanket concept
|
Jin, Xue Zhou
|
|
2018
|
136 |
PB |
p. 958-963
|
artikel
|
| 14 |
Beam diagnostics of an ECR ion source on LIPAc injector for prototype IFMIF beam accelerator
|
Bolzon, Benoît
|
|
2018
|
136 |
PB |
p. 1300-1305
|
artikel
|
| 15 |
Beam extraction characteristics of a low-energy, high-current pulsed ion source of a versatile experiment spherical torus neutral beam injector
|
Kim, Tae-Seong
|
|
2018
|
136 |
PB |
p. 1365-1369
|
artikel
|
| 16 |
Bonding techniques and performance qualification of plasma facing components for Korean fusion research
|
Kim, Suk-Kwon
|
|
2018
|
136 |
PB |
p. 1510-1513
|
artikel
|
| 17 |
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
|
Ying, Alice
|
|
2018
|
136 |
PB |
p. 1153-1160
|
artikel
|
| 18 |
CFD-based shape optimization on cross-section of monoblock fusion divertor cooling channel for minimizing local heat flux
|
Lim, Do Kyun
|
|
2018
|
136 |
PB |
p. 1100-1105
|
artikel
|
| 19 |
CFD simulation of pressure wave propagation in the helium coolant tube break accident of DFLL-TBM
|
Sun, Qian
|
|
2018
|
136 |
PB |
p. 950-957
|
artikel
|
| 20 |
Characteristic research of pellet injection system in KSTAR
|
Park, SooHwan
|
|
2018
|
136 |
PB |
p. 1094-1099
|
artikel
|
| 21 |
Comparison of shear strength and failure mechanisms of lap joint between REBCO tapes bonded by different joining techniques
|
Aparicio, Luis Ernesto
|
|
2018
|
136 |
PB |
p. 1196-1201
|
artikel
|
| 22 |
Completion of ENEA’s casing procurement forJT-60SA toroidal field coils
|
Rossi, Paolo
|
|
2018
|
136 |
PB |
p. 1359-1364
|
artikel
|
| 23 |
Computational thermofluid-dynamic analysis of DEMO divertor cassette body cooling circuit
|
Di Maio, P.A.
|
|
2018
|
136 |
PB |
p. 1588-1592
|
artikel
|
| 24 |
Conceptual studies of gamma ray diagnostics for DEMO control
|
Giacomelli, L.
|
|
2018
|
136 |
PB |
p. 1494-1498
|
artikel
|
| 25 |
Corrosion–erosion and mass transfer dynamic behaviors of reduced activation ferritic/martensitic steel in a nonisothermal Pb-17Li system
|
Kondo, Masatoshi
|
|
2018
|
136 |
PB |
p. 1581-1587
|
artikel
|
| 26 |
Cracks avoidance with a modified solid tungsten divertor in ASDEX Upgrade
|
Zammuto, I.
|
|
2018
|
136 |
PB |
p. 1052-1057
|
artikel
|
| 27 |
Cylindrical breeding blankets for fusion reactors
|
Tanigawa, Hisashi
|
|
2018
|
136 |
PB |
p. 1221-1225
|
artikel
|
| 28 |
Damage and melting of ITER-like flat-type tungsten castellated blocks exposed to long pulse H-mode plasmas
|
Hong, Suk-Ho
|
|
2018
|
136 |
PB |
p. 1518-1522
|
artikel
|
| 29 |
DEMO design using the SYCOMORE system code: Influence of technological constraints on the reactor performances
|
Reux, C.
|
|
2018
|
136 |
PB |
p. 1572-1576
|
artikel
|
| 30 |
Dependability assessment of ITER cask & plug remote handling system during nuclear maintenance operations
|
van Houtte, D.
|
|
2018
|
136 |
PB |
p. 1342-1347
|
artikel
|
| 31 |
Design and analysis of a new configuration of secondary circuit of the EU-DEMO fusion power plant using GateCycle
|
Malinowski, Leszek
|
|
2018
|
136 |
PB |
p. 1149-1152
|
artikel
|
| 32 |
Design and CFD analysis of hypervapotron-typed ion dump for KSTAR NBI-2 system
|
Kim, K.M.
|
|
2018
|
136 |
PB |
p. 1032-1037
|
artikel
|
| 33 |
Design and status of the new WEST IR thermography system
|
Courtois, X.
|
|
2018
|
136 |
PB |
p. 1499-1504
|
artikel
|
| 34 |
Design constraints on new vacuum components of RFX-mod2 upgrade using electrical modeling of reversed field pinch plasma
|
Cavazzana, Roberto
|
|
2018
|
136 |
PB |
p. 1209-1213
|
artikel
|
| 35 |
Design features and commissioning of pulse arc plasma source and power supply system for the VEST neutral beam injection system
|
Jung, Bong-Ki
|
|
2018
|
136 |
PB |
p. 1614-1617
|
artikel
|
| 36 |
Design of remote handling, nuclear and vacuum compatible connectors for mineral insulated thermocouples of ITER neutral beam injectors
|
Dalla Palma, Mauro
|
|
2018
|
136 |
PB |
p. 1191-1195
|
artikel
|
| 37 |
Design optimization and analysis of CN HCCB TBM-set
|
Wu, Xinghua
|
|
2018
|
136 |
PB |
p. 839-846
|
artikel
|
| 38 |
Detailed design of the RFX-mod2 machine load assembly
|
Peruzzo, Simone
|
|
2018
|
136 |
PB |
p. 1605-1613
|
artikel
|
| 39 |
Detail procedure of pressure and baking test for ITER vacuum vessel lower port stub extension
|
Moon, Hokyu
|
|
2018
|
136 |
PB |
p. 1514-1517
|
artikel
|
| 40 |
Deuterium retention in neutron-irradiated single-crystal tungsten
|
Shimada, M.
|
|
2018
|
136 |
PB |
p. 1161-1167
|
artikel
|
| 41 |
Development and qualification of functional materials for the European HCPB TBM
|
Zmitko, M.
|
|
2018
|
136 |
PB |
p. 1376-1385
|
artikel
|
| 42 |
Development and qualification of the ITER port plug handling process
|
Josseaume, Fabien
|
|
2018
|
136 |
PB |
p. 902-907
|
artikel
|
| 43 |
Development and validation of the blanket First Wall mock-up model in RELAP5-3D
|
Di Marcello, Valentino
|
|
2018
|
136 |
PB |
p. 1534-1539
|
artikel
|
| 44 |
Development of the safety code AINA for the European DEMO designs
|
Baeza, Eduard
|
|
2018
|
136 |
PB |
p. 1084-1088
|
artikel
|
| 45 |
Direct numerical simulation of liquid metal free-surface turbulent flows imposed on wall-normal magnetic field
|
Yamamoto, Yoshinobu
|
|
2018
|
136 |
PB |
p. 925-930
|
artikel
|
| 46 |
Editorial Board
|
|
|
2018
|
136 |
PB |
p. ii
|
artikel
|
| 47 |
Effect of induction heating on flaw generation and expansion
|
Richou, M.
|
|
2018
|
136 |
PB |
p. 1273-1277
|
artikel
|
| 48 |
Effect of neutral leaks on pumping efficiency in 3D DEMO divertor configuration
|
Varoutis, Stylianos
|
|
2018
|
136 |
PB |
p. 1135-1139
|
artikel
|
| 49 |
Effect of Resonant Magnetic Perturbation on erosion of divertor region in KSTAR
|
Bang, Eunnam
|
|
2018
|
136 |
PB |
p. 1242-1246
|
artikel
|
| 50 |
Effect of the length of the poloidal ducts on flow balancing in a liquid metal blanket
|
Rhodes, Tyler J.
|
|
2018
|
136 |
PB |
p. 847-851
|
artikel
|
| 51 |
Effects of test environment on high temperature fatigue properties of reduced activation ferritic/martensitic steel, F82H
|
Hirose, Takanori
|
|
2018
|
136 |
PB |
p. 1073-1076
|
artikel
|
| 52 |
Effects of tungsten and carbon rough surfaces on the material mixing and impurity erosion/deposition
|
Dai, Shuyu
|
|
2018
|
136 |
PB |
p. 897-901
|
artikel
|
| 53 |
Electron temperature estimation using the Pulse Height Analysis system at Wendelstein 7-X stellarator
|
Krawczyk, Natalia
|
|
2018
|
136 |
PB |
p. 1291-1294
|
artikel
|
| 54 |
Enhanced high-temperature mechanical properties of ARAA by thermo-mechanical processing
|
Chun, Y.B.
|
|
2018
|
136 |
PB |
p. 883-890
|
artikel
|
| 55 |
Equivalent circuit model of a rectangular RF driven hydrogen ion source for impedance matching network design
|
Huh, Sung-Ryul
|
|
2018
|
136 |
PB |
p. 1422-1427
|
artikel
|
| 56 |
Erosion-corrosion resistance of Reduced Activation Ferritic-Martensitic steels exposed to flowing liquid Lithium
|
Favuzza, P.
|
|
2018
|
136 |
PB |
p. 1417-1421
|
artikel
|
| 57 |
Estimation of neutron yields produced from SS316L, CuCrZr, and graphite targets for MeV-energy electrons toward JT-60 Tokamak fusion device
|
Sukegawa, Atsuhiko M.
|
|
2018
|
136 |
PB |
p. 1653-1657
|
artikel
|
| 58 |
EU contribution to the procurement of blanket first wall and divertor components for ITER
|
Lorenzetto, Patrick
|
|
2018
|
136 |
PB |
p. 975-982
|
artikel
|
| 59 |
EU DEMO EC system preliminary conceptual design
|
Garavaglia, Saul
|
|
2018
|
136 |
PB |
p. 1173-1177
|
artikel
|
| 60 |
Evaluation of tritium leakage rate into seawater in fusion DEMO cooling water system
|
Miyoshi, Yuya
|
|
2018
|
136 |
PB |
p. 1577-1580
|
artikel
|
| 61 |
Experimental study on the dryout point and post-dryout heat transfer in square channel
|
Bao, Hui
|
|
2018
|
136 |
PB |
p. 1012-1018
|
artikel
|
| 62 |
Exploiting information of fusion component tests for failure rate estimation: Divertor Inner Vertical Target component study case
|
Dongiovanni, Danilo Nicola
|
|
2018
|
136 |
PB |
p. 1629-1633
|
artikel
|
| 63 |
Exploring a broad spectrum of design options for DEMO
|
Kemp, R.
|
|
2018
|
136 |
PB |
p. 970-974
|
artikel
|
| 64 |
Fabrication and characterization of Be-Zr-Ti ternary beryllide pebbles
|
Kim, Jae-Hwan
|
|
2018
|
136 |
PB |
p. 864-868
|
artikel
|
| 65 |
Final status of water detritiation system (WDS) for Cernavoda Tritium removal facility (CTRF)
|
Zamfirache, Marius
|
|
2018
|
136 |
PB |
p. 1038-1040
|
artikel
|
| 66 |
Fusion DEMO reactor design based on nuclear analysis
|
Someya, Youji
|
|
2018
|
136 |
PB |
p. 1306-1312
|
artikel
|
| 67 |
Fusion power plants, fission and conventional power plants. Radioactivity, radiotoxicity, radioactive waste
|
Zucchetti, Massimo
|
|
2018
|
136 |
PB |
p. 1529-1533
|
artikel
|
| 68 |
Generation of a plasma neutron source for Monte Carlo neutron transport calculations in the tokamak JET
|
Štancar, Žiga
|
|
2018
|
136 |
PB |
p. 1047-1051
|
artikel
|
| 69 |
Heat loading behavior and thermomechanical analyses on plasma spray tungsten coated reduced-activation ferritic/martensitic steel
|
Tokunaga, K.
|
|
2018
|
136 |
PB |
p. 1624-1628
|
artikel
|
| 70 |
High temperature oedometric compression of Li2TiO3 pebble beds for Indian TBM
|
Desu, Raghuram Karthik
|
|
2018
|
136 |
PB |
p. 945-949
|
artikel
|
| 71 |
Hydraulic modeling of a segment of the EU DEMO HCPB breeding blanket back supporting structure
|
Bertinetti, Andrea
|
|
2018
|
136 |
PB |
p. 1186-1190
|
artikel
|
| 72 |
Hydrodynamic characteristics of mixed catalytic packing for heavy water detritiation
|
Gheorghe, Ionita
|
|
2018
|
136 |
PB |
p. 1252-1255
|
artikel
|
| 73 |
Hydrogen recovery from metal particle dispersed salt by selective microwave heating
|
Watanabe, Takashi
|
|
2018
|
136 |
PB |
p. 1396-1399
|
artikel
|
| 74 |
Impact of the monoblock thickness in an ITER-like configuration of DEMO divertor
|
Maviglia, Fabio
|
|
2018
|
136 |
PB |
p. 1322-1326
|
artikel
|
| 75 |
Investigation of beryllium pebbles produced by powder metallurgy for HCPB breeding blanket
|
Kupriyanov, I.B.
|
|
2018
|
136 |
PB |
p. 1077-1083
|
artikel
|
| 76 |
Investigation of vibrations caused by the steam condensation at sub-atmospheric condition in VVPSS
|
Lo Frano, Rosa
|
|
2018
|
136 |
PB |
p. 1433-1437
|
artikel
|
| 77 |
Investigation on the “advanced-plus” Helium Cooled Lithium Lead Breeding Blanket design concept for TBR enhancement regarding thermal and mechanical behavior
|
Boullon, Rémi
|
|
2018
|
136 |
PB |
p. 1231-1236
|
artikel
|
| 78 |
ITER TBM Program and associated system engineering
|
Giancarli, Luciano M.
|
|
2018
|
136 |
PB |
p. 815-821
|
artikel
|
| 79 |
ITER upper port wide angle viewing system optical design and performance analysis
|
Verlaan, Ad
|
|
2018
|
136 |
PB |
p. 936-944
|
artikel
|
| 80 |
Li vaporization property of Li8ZrO6 and Li5AlO4 as tritium breeders
|
Shin-mura, Kiyoto
|
|
2018
|
136 |
PB |
p. 869-873
|
artikel
|
| 81 |
Maintainability of the helical reactor FFHR-c1 equipped with the liquid metal divertor and cartridge-type blankets
|
Miyazawa, Junichi
|
|
2018
|
136 |
PB |
p. 1278-1285
|
artikel
|
| 82 |
Manufacturing and testing of ITER-like divertor plasma facing mock-ups for DEMO
|
Visca, Eliseo
|
|
2018
|
136 |
PB |
p. 1593-1596
|
artikel
|
| 83 |
MCNP model of the ITER Tokamak Complex
|
López-Revelles, A.J.
|
|
2018
|
136 |
PB |
p. 859-863
|
artikel
|
| 84 |
Metal Foil Pump performance aspects in view of the implementation of Direct Internal Recycling for future fusion fuel cycles
|
Peters, B.J.
|
|
2018
|
136 |
PB |
p. 1467-1471
|
artikel
|
| 85 |
Modeling of chemical reactions of beryllium/beryllide pebbles with steam for hydrogen safety design of water-cooled DEMO
|
Nakamura, Makoto M.
|
|
2018
|
136 |
PB |
p. 1484-1488
|
artikel
|
| 86 |
Modeling of fuel retention in the upper tungsten divertor of EAST from attached to detached divertor plasma
|
Sang, Chaofeng
|
|
2018
|
136 |
PB |
p. 908-913
|
artikel
|
| 87 |
Modelling an in-vessel loss of coolant accident in the EU DEMO WCLL breeding blanket with the GETTHEM code
|
Froio, Antonio
|
|
2018
|
136 |
PB |
p. 1226-1230
|
artikel
|
| 88 |
Modelling of the neutron production in a mixed beam DT neutron generator
|
Čufar, Aljaž
|
|
2018
|
136 |
PB |
p. 1089-1093
|
artikel
|
| 89 |
Molecular Dynamics Simulation of Primary Damage in β-Li2TiO3
|
Suhail, Mohammed
|
|
2018
|
136 |
PB |
p. 914-919
|
artikel
|
| 90 |
Molten salt thermal conductivity enhancement by mixing nanoparticles
|
Ueki, Yoshitaka
|
|
2018
|
136 |
PB |
p. 1295-1299
|
artikel
|
| 91 |
Multi-Module vs. Single-Module concept: Comparison of thermomechanical performances for the DEMO Water-Cooled Lithium Lead breeding blanket
|
Bongiovì, G.
|
|
2018
|
136 |
PB |
p. 1472-1478
|
artikel
|
| 92 |
Neutronic analyses in support of the WCLL DEMO design development
|
Moro, Fabio
|
|
2018
|
136 |
PB |
p. 1260-1264
|
artikel
|
| 93 |
Neutronic effects of diagnostic shield module length on radiation environment of ITER diagnostic generic upper port plug
|
Serikov, Arkady
|
|
2018
|
136 |
PB |
p. 920-924
|
artikel
|
| 94 |
Nuclear analysis of the HCLL “Advanced-Plus” breeding blanket
|
Jaboulay, Jean-Charles
|
|
2018
|
136 |
PB |
p. 1540-1544
|
artikel
|
| 95 |
Numerical assessment of the thermomechanical behaviour of the DEMO Water-Cooled Lithium Lead inboard blanket equatorial module
|
Di Maio, P.A.
|
|
2018
|
136 |
PB |
p. 1178-1185
|
artikel
|
| 96 |
Numerical investigation of the pebble bed structures for HCCB TBM
|
Gong, Baoping
|
|
2018
|
136 |
PB |
p. 1444-1451
|
artikel
|
| 97 |
Numerical simulation of Li pellet ablation in the H-mode pedestal region
|
Sun, Jizhong
|
|
2018
|
136 |
PB |
p. 834-838
|
artikel
|
| 98 |
On the thermal and thermomechanical assessment of the “Optimized Conservative” helium-cooled lithium lead breeding blanket concept for DEMO
|
Bongiovì, G.
|
|
2018
|
136 |
PB |
p. 1370-1375
|
artikel
|
| 99 |
On the thermal-hydraulic optimization of DEMO divertor plasma facing components cooling circuit
|
Di Maio, P.A.
|
|
2018
|
136 |
PB |
p. 1438-1443
|
artikel
|
| 100 |
Optimised energy group structures for fusion activation calculations
|
Thomas, Fred
|
|
2018
|
136 |
PB |
p. 1479-1483
|
artikel
|
| 101 |
Optimization of the pressure drops in the helium in-module manifolds of the EU DEMO “Optimized Conservative” HCLL Breeding Blanket
|
Domalapally, Phani Kumar
|
|
2018
|
136 |
PB |
p. 852-858
|
artikel
|
| 102 |
Overview of the DEMO conceptual design activity in Japan
|
Tobita, Kenji
|
|
2018
|
136 |
PB |
p. 1024-1031
|
artikel
|
| 103 |
Overview of the ITER remote maintenance design and of the development activities in Europe
|
Damiani, C.
|
|
2018
|
136 |
PB |
p. 1117-1124
|
artikel
|
| 104 |
Performance test of radiation detectors developed for ITER-TBM
|
Angelone, M.
|
|
2018
|
136 |
PB |
p. 1386-1390
|
artikel
|
| 105 |
Pipe Maintenance Tooling development for the ITER Divertor Remote Handling System
|
Lamb, Chris
|
|
2018
|
136 |
PB |
p. 983-987
|
artikel
|
| 106 |
Plasma exhaust and divertor studies in Japan and Europe broader approach, DEMO design activity
|
Asakura, Nobuyuki
|
|
2018
|
136 |
PB |
p. 1214-1220
|
artikel
|
| 107 |
Pre-conceptual design of DEMO upper port duct bellows
|
Costa Garrido, Oriol
|
|
2018
|
136 |
PB |
p. 1130-1134
|
artikel
|
| 108 |
Predictive modeling of HL-2M divertor operation by SOLPS-ITER
|
Cao, Chengzhi
|
|
2018
|
136 |
PB |
p. 822-827
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artikel
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| 109 |
Preliminary design and structural analyses of DEMO bioshield roof
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Ciupiński, Łukasz
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2018
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136 |
PB |
p. 1461-1466
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artikel
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| 110 |
Preliminary design of EU DEMO helium-cooled breeding blanket primary heat transfer system
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Moscato, I.
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2018
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136 |
PB |
p. 1567-1571
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artikel
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| 111 |
Preliminary study of DEMO disruptions due to component failures
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Pinna, Tonio
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2018
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136 |
PB |
p. 1265-1268
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artikel
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| 112 |
Preparation for commissioning of materials detritiation facility at Culham Science Centre
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Kresina, Michal
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2018
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136 |
PB |
p. 1391-1395
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artikel
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| 113 |
Progress in the design of the superconducting magnets for the EU DEMO
|
Corato, V.
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2018
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136 |
PB |
p. 1597-1604
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artikel
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| 114 |
Quantification of main wall erosion/deposition pattern in n = 2 RMP KSTAR H-mode plasmas
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Son, S.H.
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2018
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136 |
PB |
p. 1317-1321
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artikel
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| 115 |
RAMI: The main challenge of fusion nuclear technologies
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Maisonnier, David
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2018
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136 |
PB |
p. 1202-1208
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artikel
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| 116 |
Recent accomplishments of the fusion safety program at the Idaho National Laboratory
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Merrill, Brad J.
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2018
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136 |
PB |
p. 1106-1111
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artikel
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| 117 |
Safety classification of mechanical components for fusion application
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Gonzalez de Vicente, Sehila M.
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2018
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136 |
PB |
p. 1237-1241
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artikel
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| 118 |
Shutdown dose rate calculation along the ITER IVVS port
|
Flammini, Davide
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2018
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136 |
PB |
p. 1404-1407
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artikel
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| 119 |
Shutdown dose rate measurements after the 2016 Deuterium-Deuterium campaign at JET
|
Fonnesu, N.
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2018
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136 |
PB |
p. 1348-1353
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artikel
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| 120 |
Shutdown dose rate neutronics experiment during high performances DD operations at JET
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Villari, R.
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2018
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136 |
PB |
p. 1545-1549
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artikel
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| 121 |
Simplified models of the ITER vacuum vessel for global seismic analyses
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Di Martino, Fabrizio
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2018
|
136 |
PB |
p. 1354-1358
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artikel
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| 122 |
Simulation of electromagnetic VDE plasma effects on divertor structures of DEMO
|
Cocilovo, Valter
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2018
|
136 |
PB |
p. 1452-1460
|
artikel
|
| 123 |
Simulation of the gas puffing fueling on the HL-2A tokamak using SOLPS
|
Sang, Chaofeng
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2018
|
136 |
PB |
p. 1041-1046
|
artikel
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| 124 |
Simulation study of the radiative divertor with argon seeding for CFETR phase II
|
Zhou, Y.F.
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2018
|
136 |
PB |
p. 931-935
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artikel
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| 125 |
Smart first wall materials for intrinsic safety of a fusion power plant
|
Litnovsky, A.
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2018
|
136 |
PB |
p. 878-882
|
artikel
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| 126 |
Solutions to fix the shine-through at the hypervapotrons of SPIDER beam dump
|
Zaupa, M.
|
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2018
|
136 |
PB |
p. 1634-1639
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artikel
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| 127 |
Status of EU DEMO heat transport and power conversion systems
|
Barucca, L.
|
|
2018
|
136 |
PB |
p. 1557-1566
|
artikel
|
| 128 |
Status of the EU DEMO HCLL breeding blanket design development
|
Aubert, Julien
|
|
2018
|
136 |
PB |
p. 1428-1432
|
artikel
|
| 129 |
Status of the final design of the EC UPP launcher
|
Spaeh, Peter
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|
2018
|
136 |
PB |
p. 1058-1062
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artikel
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| 130 |
Status of water cooled ceramic breeder blanket development
|
Kawamura, Yoshinori
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2018
|
136 |
PB |
p. 1550-1556
|
artikel
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| 131 |
Structural analysis for final design of ITER sector In-pit Assembly Tool
|
Ha, Min-Su
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2018
|
136 |
PB |
p. 1019-1023
|
artikel
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| 132 |
Studies of the plasma vertical instability and its stabilized concepts in JA and EU broader approach, DEMO design activity
|
Utoh, Hiroyasu
|
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2018
|
136 |
PB |
p. 874-877
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artikel
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| 133 |
Study of EU DEMO WCLL breeding blanket and primary heat transfer system integration
|
Martelli, Emanuela
|
|
2018
|
136 |
PB |
p. 828-833
|
artikel
|
| 134 |
Study of impurity behaviour for first magnetic configuration changes in W7-X plasmas by means of PHA spectra
|
Czarnecka, Agata
|
|
2018
|
136 |
PB |
p. 1286-1290
|
artikel
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| 135 |
Technical innovations for ITER Edge Thomson scattering measurement system
|
Yatsuka, Eiichi
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|
2018
|
136 |
PB |
p. 1068-1072
|
artikel
|
| 136 |
The design and application of Alfvén antennas in J-TEXT tokamak
|
He, Jiyang
|
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2018
|
136 |
PB |
p. 1400-1403
|
artikel
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| 137 |
The European ITER Test Blanket Modules: Fabrication R&D progress for HCLL and HCPB
|
Forest, Laurent
|
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2018
|
136 |
PB |
p. 1408-1416
|
artikel
|
| 138 |
The possible effect of high magnetic fields on the aqueous corrosion behaviour of Eurofer
|
Burrows, R.
|
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2018
|
136 |
PB |
p. 1000-1006
|
artikel
|
| 139 |
Thermal analysis of Test Divertor Unit Scraper Element for Wendelstein 7-X
|
Lumsdaine, Arnold
|
|
2018
|
136 |
PB |
p. 964-969
|
artikel
|
| 140 |
Thermomechanical analysis supporting the preliminary engineering design of DONES target assembly
|
Arena, P.
|
|
2018
|
136 |
PB |
p. 1332-1336
|
artikel
|
| 141 |
Thermo-mechanical stress analysis of the water cooled DEMO First Wall mock-up components
|
Kamenický, Robin
|
|
2018
|
136 |
PB |
p. 1618-1623
|
artikel
|
| 142 |
The safety report of future fusion power plants
|
Perrault, Didier
|
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2018
|
136 |
PB |
p. 1256-1259
|
artikel
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| 143 |
Tokamak systems analyses using a fast 1D transport solver: Models and assessments
|
Rivas, Jose Carlos
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2018
|
136 |
PB |
p. 1125-1129
|
artikel
|
| 144 |
Traveling-wave antenna for the current drive using the fast wave in the lower hybrid-frequency range in the Versatile Experiment Spherical Torus (VEST)
|
Lee, Hyunwoo
|
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2018
|
136 |
PB |
p. 1505-1509
|
artikel
|
| 145 |
Tritium release from molten salt FLiNaK under low flux neutron irradiation with an AmBe neutron source
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Kumagai, Kohki
|
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2018
|
136 |
PB |
p. 1269-1272
|
artikel
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| 146 |
Tritium supply and use: a key issue for the development of nuclear fusion energy
|
Pearson, Richard J.
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|
2018
|
136 |
PB |
p. 1140-1148
|
artikel
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| 147 |
Tritium transport model at the minimal functional unit level for HCLL and WCLL breeding blankets of DEMO
|
Candido, Luigi
|
|
2018
|
136 |
PB |
p. 1327-1331
|
artikel
|
| 148 |
Uncertainties identification and initial evaluation in the accident analyses of fusion breeder blankets
|
Panayotov, Dobromir
|
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2018
|
136 |
PB |
p. 993-999
|
artikel
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| 149 |
Virtual Reality: Lessons learned from WEST design and perspectives for nuclear environment
|
Meunier, Lionel
|
|
2018
|
136 |
PB |
p. 1337-1341
|
artikel
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