| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A composite beam model for the mechanical analysis of superconducting magnet pancakes
|
Schrefler, B.A
|
|
1990
|
96-97 |
2 |
p. 103-123
21 p.
|
artikel
|
| 2 |
Activation product transport using TRACT: ORE estimation of an ITER cooling loop
|
Karditsas, Panos J.
|
|
1999
|
96-97 |
2 |
p. 169-185
17 p.
|
artikel
|
| 3 |
Advanced power core system for the ARIES-AT power plant
|
Raffray, A.R.
|
|
2007
|
96-97 |
2 |
p. 217-236
20 p.
|
artikel
|
| 4 |
Afterheat transient in ITER after a total loss of coolant accident
|
Andritsos, F.
|
|
1991
|
96-97 |
2 |
p. 113-119
7 p.
|
artikel
|
| 5 |
Aluminum-assisted joining of beryllium to copper for fusion applications
|
Cadden, C.H
|
|
1997
|
96-97 |
2 |
p. 287-298
12 p.
|
artikel
|
| 6 |
An advanced computational algorithm for systems analysis of tokamak power plants
|
Dragojlovic, Zoran
|
|
2010
|
96-97 |
2 |
p. 243-265
23 p.
|
artikel
|
| 7 |
Analysis of the magnetomechanical behavior of a ferromagnetic beam plate
|
Miya, K.
|
|
1987
|
96-97 |
2 |
p. 167-180
14 p.
|
artikel
|
| 8 |
An Eulerian MHD model for the analysis of magnetic flux compression by expanding diamagnetic fusion plasma sphere
|
Sijoy, C.D.
|
|
2012
|
96-97 |
2 |
p. 104-117
14 p.
|
artikel
|
| 9 |
A new optimized design concept of the switching network resistors of the large ITER-FEAT tokamak
|
Bareyt, B.
|
|
2002
|
96-97 |
2 |
p. 127-140
14 p.
|
artikel
|
| 10 |
An experimental and numerical investigation of post-CHF heat transfer for one-sided heat load with highly sub-cooled flow boiling
|
Divavin, V.
|
|
1996
|
96-97 |
2 |
p. 189-200
12 p.
|
artikel
|
| 11 |
An injector device for producing clean-surface liquid metal samples of Li, Ga and Sn–Li in vacuum
|
Baldwin, M.J.
|
|
2004
|
96-97 |
2 |
p. 107-113
7 p.
|
artikel
|
| 12 |
A novel approach to linearization of the electromagnetic parameters of tokamaks with an iron core
|
Fu, P.
|
|
2002
|
96-97 |
2 |
p. 119-125
7 p.
|
artikel
|
| 13 |
Application of glow discharges for tritium removal from JT-60U vacuum vessel
|
Nakamura, Hirofumi
|
|
2004
|
96-97 |
2 |
p. 163-173
11 p.
|
artikel
|
| 14 |
Application of the time—space finite element method to the thermomechanical analysis of the first wall
|
Teramae, T.
|
|
1987
|
96-97 |
2 |
p. 155-165
11 p.
|
artikel
|
| 15 |
A repetitive pellet injection system for steady state fuelling in EAST superconducting tokamak
|
Li, C.Z.
|
|
2014
|
96-97 |
2 |
p. 99-103
5 p.
|
artikel
|
| 16 |
ARIES-ST design point selection
|
Miller, Ronald L.
|
|
2003
|
96-97 |
2 |
p. 199-213
15 p.
|
artikel
|
| 17 |
ARIES-ST nuclear analysis and shield design
|
El-Guebaly, Laila A
|
|
2003
|
96-97 |
2 |
p. 263-284
22 p.
|
artikel
|
| 18 |
ARIES-ST safety design and analysis
|
Khater, H.Y
|
|
2003
|
96-97 |
2 |
p. 285-301
17 p.
|
artikel
|
| 19 |
ARIES-ST Special Issue Editorial
|
Najmabadi, Farrokh
|
|
2003
|
96-97 |
2 |
p. 141-
1 p.
|
artikel
|
| 20 |
A special correcting winding for the l =2 torsatron with split-type helical coils
|
Kotenko, V.G.
|
|
2012
|
96-97 |
2 |
p. 118-123
6 p.
|
artikel
|
| 21 |
A study of time-dependent, low energy (2 × 10-4 eV<E<0.2eV) neutron spectra and tritium breeding in 3He + C blanket of a fusion reactor
|
Gupta, Sanjay
|
|
1996
|
96-97 |
2 |
p. 117-125
9 p.
|
artikel
|
| 22 |
A thermal cycling durability test of tungsten copper duplex structures for use as a divertor plate
|
Seki, M.
|
|
1987
|
96-97 |
2 |
p. 205-213
9 p.
|
artikel
|
| 23 |
Beam divergence and power loading on the beamline components of the negative-ion based NBI system for JT-60U
|
Hu, Liqun
|
|
2001
|
96-97 |
2 |
p. 321-330
10 p.
|
artikel
|
| 24 |
Beryllium application in ITER plasma facing components
|
Raffray, A.R
|
|
1997
|
96-97 |
2 |
p. 261-286
26 p.
|
artikel
|
| 25 |
Beryllium armour produced by evaporation–condensation technique
|
Anisimov, A
|
|
1997
|
96-97 |
2 |
p. 253-259
7 p.
|
artikel
|
| 26 |
Beryllium dust generation resulting from plasma bombardment
|
Doerner, R.
|
|
1997
|
96-97 |
2 |
p. 325-331
7 p.
|
artikel
|
| 27 |
Characterization of advanced cyanate ester/epoxy insulation systems before and after reactor irradiation
|
Prokopec, R.
|
|
2010
|
96-97 |
2 |
p. 227-233
7 p.
|
artikel
|
| 28 |
Chemical compound formation and its analysis in the beryllium-carbon binary system at elevated temperatures
|
Ashida, Kan
|
|
1997
|
96-97 |
2 |
p. 307-315
9 p.
|
artikel
|
| 29 |
Commissioning the ICRF system and an ICRF assisted discharge cleaning at the KSTAR
|
Kwak, Jong-Gu
|
|
2010
|
96-97 |
2 |
p. 169-173
5 p.
|
artikel
|
| 30 |
Compatibility aspects of the Pb-17Li martensitic steel-H2O system
|
Donato, A.
|
|
1996
|
96-97 |
2 |
p. 127-144
18 p.
|
artikel
|
| 31 |
Computational study on eddy current characteristics in a super conducting tokamak
|
Abe, Mitsushi
|
|
2002
|
96-97 |
2 |
p. 191-209
19 p.
|
artikel
|
| 32 |
Conceptual design of the FAST load assembly
|
Cucchiaro, A.
|
|
2010
|
96-97 |
2 |
p. 174-180
7 p.
|
artikel
|
| 33 |
Conceptual design of the liquid metal laboratory of the TECHNOFUSION facility
|
Abánades, A.
|
|
2012
|
96-97 |
2 |
p. 161-166
6 p.
|
artikel
|
| 34 |
Convective heat transfer enhancement when using gas-solid particle two phase coolant for the Tokamak type reactor first wall cooling
|
Epinatiev, A.M.
|
|
1996
|
96-97 |
2 |
p. 109-115
7 p.
|
artikel
|
| 35 |
Copper vapor laser application for surface monitoring of divertor and first wall in ITER
|
Buzhinskij, O.I.
|
|
2002
|
96-97 |
2 |
p. 141-155
15 p.
|
artikel
|
| 36 |
Corrigendum to “Letter to the Editor: Heating of deuteron implanted A1 on electron bombardment and its possible relation to ‘cold fusion’ experiment”
|
Kamada, K.
|
|
2002
|
96-97 |
2 |
p. 217-
1 p.
|
artikel
|
| 37 |
Creep surge effect under cyclic irradiation of structural materials for fusion reactors
|
Tsepelev, A.B.
|
|
2004
|
96-97 |
2 |
p. 79-85
7 p.
|
artikel
|
| 38 |
Design analysis of plasma position control in SST1
|
Bandyopadhyay, I.
|
|
2001
|
96-97 |
2 |
p. 151-166
16 p.
|
artikel
|
| 39 |
Design and development of five-channel interference filter polychromator for SST-1 Thomson scattering system
|
Thomas, Jinto
|
|
2012
|
96-97 |
2 |
p. 134-140
7 p.
|
artikel
|
| 40 |
Design criteria and current status of LHCD system on SST1 machine
|
Bora, D.
|
|
2007
|
96-97 |
2 |
p. 141-152
12 p.
|
artikel
|
| 41 |
Design of equilibrium field control coil system of TPE-RX
|
Sato, F
|
|
2001
|
96-97 |
2 |
p. 263-273
11 p.
|
artikel
|
| 42 |
Designs of contraction nozzle and concave back-wall for IFMIF target
|
Ida, Mizuho
|
|
2004
|
96-97 |
2 |
p. 95-106
12 p.
|
artikel
|
| 43 |
Design study of a tritium transport package for future fusion reactors
|
O’hira, S.
|
|
1999
|
96-97 |
2 |
p. 187-195
9 p.
|
artikel
|
| 44 |
Deuterium trapping by carbon materials for tokamak plasma-facing components
|
Gorodetsky, A.E.
|
|
1998
|
96-97 |
2 |
p. 129-145
17 p.
|
artikel
|
| 45 |
Development of a 30m long Nb3Al superconducting conductor jacketed with a round-in-square type stainless steel conduit for the toroidal field coils in JT-60SC
|
Tsuchiya, Katsuhiko
|
|
2004
|
96-97 |
2 |
p. 131-140
10 p.
|
artikel
|
| 46 |
Development of plasma stored energy feedback control and its application to high performance discharges on JT-60U
|
Oikawa, T.
|
|
2004
|
96-97 |
2 |
p. 175-183
9 p.
|
artikel
|
| 47 |
Development of super high power klystron-system for JT-60 LHRF heating and current drive
|
Imai, Tsuyoshi
|
|
1990
|
96-97 |
2 |
p. 177-185
9 p.
|
artikel
|
| 48 |
Development status of KSTAR 5GHz LHCD system
|
Park, S.
|
|
2010
|
96-97 |
2 |
p. 197-204
8 p.
|
artikel
|
| 49 |
Dimensional analysis of critical heat flux in subcooled water flow under one-side heating conditions for fusion application
|
Boscary, J.
|
|
1998
|
96-97 |
2 |
p. 147-171
25 p.
|
artikel
|
| 50 |
Disruption induced mechanical loads calculated with a coupled 3-D eddy current/2-D MHD plasma model
|
Jordan, T.
|
|
1998
|
96-97 |
2 |
p. 173-187
15 p.
|
artikel
|
| 51 |
Divertor target engineering for fusion reactors
|
Thompson, V.K
|
|
1990
|
96-97 |
2 |
p. 187-199
13 p.
|
artikel
|
| 52 |
Dynamics and energy flow in a disrupting tokamak plasma
|
Merrill, B.J.
|
|
1991
|
96-97 |
2 |
p. 163-180
18 p.
|
artikel
|
| 53 |
Eddy current experiments with closely placed solid boxes simulating a next step fusion device
|
Abe, Mitsushi
|
|
2002
|
96-97 |
2 |
p. 179-190
12 p.
|
artikel
|
| 54 |
Editorial
|
|
|
1997
|
96-97 |
2 |
p. 227-
1 p.
|
artikel
|
| 55 |
Editorial
|
|
|
1997
|
96-97 |
2 |
p. 225-
1 p.
|
artikel
|
| 56 |
Effect of electron beam irradiation on fracture and fatigue characteristics of TZM
|
Denda, Takeshi
|
|
1990
|
96-97 |
2 |
p. 201-208
8 p.
|
artikel
|
| 57 |
Electromagnetic analysis of ITER generic equatorial port plug designs during three plasma current disruption cases
|
Guirao, J.
|
|
2012
|
96-97 |
2 |
p. 141-155
15 p.
|
artikel
|
| 58 |
Electron cyclotron resonance discharge cleaning by using LHRF system on JT-60U
|
Ushigusa, K
|
|
1999
|
96-97 |
2 |
p. 137-144
8 p.
|
artikel
|
| 59 |
Engineering aspects of a steady state tokamak reactor (SSTR)
|
Nishio, S.
|
|
1991
|
96-97 |
2 |
p. 121-135
15 p.
|
artikel
|
| 60 |
Engineering design of the National Spherical Torus Experiment
|
Neumeyer, C
|
|
2001
|
96-97 |
2 |
p. 275-319
45 p.
|
artikel
|
| 61 |
Enhancement of hydrogen absorption rate of Zr2Fe particles by NaOH pretreatment
|
Fukada, Satoshi
|
|
1998
|
96-97 |
2 |
p. 189-197
9 p.
|
artikel
|
| 62 |
Erratum
|
|
|
1991
|
96-97 |
2 |
p. 191-
1 p.
|
artikel
|
| 63 |
Erratum to "Advanced power core system for the ARIES-AT power plant
|
|
|
2007
|
96-97 |
2 |
p. 215-
1 p.
|
artikel
|
| 64 |
Exact solutions of problems about optimum compression of gas by cylindrical and spherical shock waves
|
Farshi, E.
|
|
2002
|
96-97 |
2 |
p. 99-103
5 p.
|
artikel
|
| 65 |
Experimental study on flow characteristics of a vertically falling film flow of liquid metal NaK in a transverse magnetic field
|
Li, Feng-Chen
|
|
2004
|
96-97 |
2 |
p. 185-199
15 p.
|
artikel
|
| 66 |
Exploring novel high power density concepts for attractive fusion systems
|
Abdou, Mohamed A.
|
|
1999
|
96-97 |
2 |
p. 145-167
23 p.
|
artikel
|
| 67 |
Fabrication of CaO insulator coatings by MOCVD for application in vanadium/lithium blankets
|
Zeng, Z.
|
|
2004
|
96-97 |
2 |
p. 87-93
7 p.
|
artikel
|
| 68 |
Fabrication of Li4SiO4 pebbles by a sol–gel technique
|
Wu, Xiangwei
|
|
2010
|
96-97 |
2 |
p. 222-226
5 p.
|
artikel
|
| 69 |
Fast data acquisition system based on digital oscilloscopes for fluctuation measurements in a long pulse JT-60U tokamak plasma
|
Matsunaga, G.
|
|
2007
|
96-97 |
2 |
p. 207-213
7 p.
|
artikel
|
| 70 |
Fast sweep of current phases in ICH antenna straps
|
Hwang, C.K.
|
|
1999
|
96-97 |
2 |
p. 127-135
9 p.
|
artikel
|
| 71 |
FEM simulation of a small EB welded mock-up and new sequence proposed to improve the final distortions
|
Guirao, J.
|
|
2010
|
96-97 |
2 |
p. 181-189
9 p.
|
artikel
|
| 72 |
Finite element analysis of magnetically induced vibrations of conductive plates
|
Lee, Jong S
|
|
1990
|
96-97 |
2 |
p. 125-141
17 p.
|
artikel
|
| 73 |
Finite element analysis with an axisymmetric model of the tritium diffusion in a ceramic blanket solution of a commercial tokamak
|
Abou Said, S.
|
|
1991
|
96-97 |
2 |
p. 181-189
9 p.
|
artikel
|
| 74 |
Fusion power core engineering for the ARIES-ST power plant
|
Tillack, M.S
|
|
2003
|
96-97 |
2 |
p. 215-261
47 p.
|
artikel
|
| 75 |
Fusion technology award for 1989
|
Lubell, Martin S
|
|
1990
|
96-97 |
2 |
p. 247-
1 p.
|
artikel
|
| 76 |
Gas recovery system for the first JET tritium experiment
|
Hemmerich, J.L.
|
|
1992
|
96-97 |
2 |
p. 161-167
7 p.
|
artikel
|
| 77 |
Geometry and expected performance of the solid tungsten outer divertor row in JET
|
Rapp, J.
|
|
2010
|
96-97 |
2 |
p. 153-160
8 p.
|
artikel
|
| 78 |
Heating of deuteron implanted Al on electron bombardment and its possible relation to ‘cold fusion’ experiment
|
Kamada, Kohji
|
|
2002
|
96-97 |
2 |
p. 219-226
8 p.
|
artikel
|
| 79 |
Heat transfer study for ITER blanket shield block cooling design
|
Kang, Weishan
|
|
2014
|
96-97 |
2 |
p. 94-98
5 p.
|
artikel
|
| 80 |
High heat flux tests on beryllium and beryllium-copper joints
|
Rödig, M.
|
|
1997
|
96-97 |
2 |
p. 317-324
8 p.
|
artikel
|
| 81 |
High power millimeter wave experiment of torus diamond window prototype for ITER EC H&CD system
|
Takahashi, K.
|
|
2013
|
96-97 |
2 |
p. 85-93
9 p.
|
artikel
|
| 82 |
High-temperature carbon-irradiation issues for the Sombrero ICF reactor
|
Munsat, Tobin
|
|
2001
|
96-97 |
2 |
p. 249-261
13 p.
|
artikel
|
| 83 |
Identification of material parameters of a thermo-mechanical model for pebble beds in fusion blankets
|
Gan, Yixiang
|
|
2007
|
96-97 |
2 |
p. 189-206
18 p.
|
artikel
|
| 84 |
Impact of edge localized mode on photo-elastic-modulator based motional Stark effect polarimetry
|
Suzuki, T.
|
|
2012
|
96-97 |
2 |
p. 188-194
7 p.
|
artikel
|
| 85 |
Importance diagrams—a novel presentation of the response of a material to neutron irradiation
|
Forrest, R.A.
|
|
1998
|
96-97 |
2 |
p. 209-235
27 p.
|
artikel
|
| 86 |
Improved framework for the maintenance of the JET intershot analysis chain
|
Dodt, D.
|
|
2013
|
96-97 |
2 |
p. 79-84
6 p.
|
artikel
|
| 87 |
Improvement of an electron beam facility as a heat source for disruption simulation experiments
|
Seki, Masahiro
|
|
1987
|
96-97 |
2 |
p. 215-220
6 p.
|
artikel
|
| 88 |
Influence of HIP pressure on tensile properties of a 14Cr ODS ferritic steel
|
Oksiuta, Z.
|
|
2014
|
96-97 |
2 |
p. 137-141
5 p.
|
artikel
|
| 89 |
Insertion of lead lithium eutectic mixture in RELAP/SCDAPSIM Mod 4.0 for Fusion Reactor Systems
|
Tiwari, Ashutosh
|
|
2012
|
96-97 |
2 |
p. 156-160
5 p.
|
artikel
|
| 90 |
Investigations of single crystal and polycrystalline metal mirrors under erosion conditions in TEXTOR
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Litnovsky, A.
|
|
2007
|
96-97 |
2 |
p. 123-132
10 p.
|
artikel
|
| 91 |
ISTTOK plasma control with the tomography diagnostic
|
Carvalho, P.J.
|
|
2010
|
96-97 |
2 |
p. 266-271
6 p.
|
artikel
|
| 92 |
Laser-assisted cleaning of beryllium-containing mirror samples from JET and PISCES-B
|
Wisse, M.
|
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2014
|
96-97 |
2 |
p. 122-130
9 p.
|
artikel
|
| 93 |
Laser coupling of the numerous flattened Gaussian beams in the fiber-based ICF laser driver
|
Huang, Z.
|
|
2013
|
96-97 |
2 |
p. 65-69
5 p.
|
artikel
|
| 94 |
Laser welding and ablation cutting process for hydraulic connections by remote handling in the ITER diagnostic port plug
|
Pak, S.
|
|
2010
|
96-97 |
2 |
p. 190-196
7 p.
|
artikel
|
| 95 |
Lifetime analysis for fusion reactor first walls and divertor plates
|
Horie, T.
|
|
1987
|
96-97 |
2 |
p. 221-231
11 p.
|
artikel
|
| 96 |
Long-term radioactive waste from fusion reactors: Part II
|
Fetter, Steve
|
|
1990
|
96-97 |
2 |
p. 239-246
8 p.
|
artikel
|
| 97 |
Low pressure tritium interaction with Inconel 625 and AISI 316 L stainless steel surfaces: an evaluation of the recombination and adsorption constants
|
Perujo, A.
|
|
1996
|
96-97 |
2 |
p. 101-108
8 p.
|
artikel
|
| 98 |
Manufacture of beryllium for fusion energy applications
|
Dombrowski, David E
|
|
1997
|
96-97 |
2 |
p. 229-242
14 p.
|
artikel
|
| 99 |
Manufacturing and assembly of the plasma- and outer vessel of the cryostat for Wendelstein 7-X
|
Hein, Bernd
|
|
2012
|
96-97 |
2 |
p. 124-127
4 p.
|
artikel
|
| 100 |
Mass transfer process of hydrogen via ceramic proton conductor membrane of electrochemical hydrogen pump
|
Kawamura, Yoshinori
|
|
2007
|
96-97 |
2 |
p. 113-121
9 p.
|
artikel
|
| 101 |
Measurement of tritium production rate distribution in natural LiAlO2/HDPE assembly irradiated by D-T neutrons
|
Jakhar, Shrichand
|
|
2012
|
96-97 |
2 |
p. 184-187
4 p.
|
artikel
|
| 102 |
Mechanical design of a PERMCAT reactor module
|
Tosti, S.
|
|
2007
|
96-97 |
2 |
p. 153-161
9 p.
|
artikel
|
| 103 |
Modeling of materials mixing behavior among beryllium, carbon and tungsten as plasma-facing materials under deuterium and tritium plasma bombardment
|
Hirooka, Yoshi
|
|
1997
|
96-97 |
2 |
p. 299-306
8 p.
|
artikel
|
| 104 |
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