| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Comparison of deuterium retention in tungsten exposed to deuterium plasma and gas
|
Ye, Xiaoqiu
|
|
|
24 |
C |
p.
|
artikel
|
| 2 |
Corrigendum to “Synergistic effects of trace ZrC/Zr on the mechanical properties and microstructure of tungsten as plasma facing materials” [Nucl. Mater. Energy 19 (2019) 225–229]
|
Zhang, T.
|
|
|
24 |
C |
p.
|
artikel
|
| 3 |
Deuterium removal from beryllium co-deposits by simulated strike-point sweeping
|
Založnik, Anže
|
|
|
24 |
C |
p.
|
artikel
|
| 4 |
Diffusion bonding effects on the adhesion of tungsten dust on tungsten surfaces
|
Tolias, P.
|
|
|
24 |
C |
p.
|
artikel
|
| 5 |
Dust sampling in WEST and tritium retention in tokamak-relevant tungsten particles
|
Peillon, S.
|
|
|
24 |
C |
p.
|
artikel
|
| 6 |
Dynamic constitutive relationship of CuCrZr alloy based on Johnson-Cook model
|
Qian, Xinyuan
|
|
|
24 |
C |
p.
|
artikel
|
| 7 |
Effect of HIP at 800 and 900 °C on microstructure and properties of extruded Be-Ti composites
|
Gaisin, Ramil
|
|
|
24 |
C |
p.
|
artikel
|
| 8 |
Effect of temperature history on swelling behavior of V-Fe binary alloy irradiated in a fast reactor Joyo
|
Fukumoto, K.
|
|
|
24 |
C |
p.
|
artikel
|
| 9 |
Effects of atom–electron energy exchange on radiation damage in zirconium
|
Zhou, Zhibing
|
|
|
24 |
C |
p.
|
artikel
|
| 10 |
Effects of interstitial carbon on the radiation tolerance of carbon-doped NiFe binary alloys from atomistic simulations
|
Ge, Guojia
|
|
|
24 |
C |
p.
|
artikel
|
| 11 |
Elucidating the microstructure of tungsten composite materials produced by powder injection molding
|
Duerrschnabel, Michael
|
|
|
24 |
C |
p.
|
artikel
|
| 12 |
Experimental study on the dynamic mechanical behaviors of silicon carbide ceramic after thermal shock
|
Li, Xiang
|
|
|
24 |
C |
p.
|
artikel
|
| 13 |
Exposures of bulk W and nanostructured W coatings to medium flux D plasmas
|
Sala, M.
|
|
|
24 |
C |
p.
|
artikel
|
| 14 |
Failure investigation of nuclear grade POCO graphite target in high energy neutrino physics through numerical simulation
|
Bidhar, Sujit
|
|
|
24 |
C |
p.
|
artikel
|
| 15 |
Fatigue properties of ferritic/martensitic steel after neutron irradiation and helium implantation
|
Nogami, Shuhei
|
|
|
24 |
C |
p.
|
artikel
|
| 16 |
Improved internal standard LIBS method used in CLF-1 exposure to liquid lithium
|
Cao, Zhi
|
|
|
24 |
C |
p.
|
artikel
|
| 17 |
Influence of 1 and 5 wt% TiC additions on the oxidation behaviour of pure tungsten
|
Pérez, Pablo
|
|
|
24 |
C |
p.
|
artikel
|
| 18 |
Influence of annealing and keV-ion implantation into tungsten on deuterium retention and permeation: The dependence on bulk and surface microstructure
|
Cai, Lu
|
|
|
24 |
C |
p.
|
artikel
|
| 19 |
Mechanical properties and stability of precipitates of an ODS steel after thermal cycling and aging
|
Oñoro, M.
|
|
|
24 |
C |
p.
|
artikel
|
| 20 |
Microstructure and mechanical properties of hot rolled ODS copper
|
Muñoz, A.
|
|
|
24 |
C |
p.
|
artikel
|
| 21 |
Microstructure, oxidation behaviour and thermal shock resistance of self-passivating W-Cr-Y-Zr alloys
|
Sal, Elisa
|
|
|
24 |
C |
p.
|
artikel
|
| 22 |
Model for hydrogen accumulation in co-deposited layers
|
Krat, S.A.
|
|
|
24 |
C |
p.
|
artikel
|
| 23 |
Relationships between depth-resolved primary radiation damage, irradiation-induced nanostructure and nanoindentation response of ion-irradiated Fe-Cr and ODS Fe-Cr alloys
|
Vogel, K.
|
|
|
24 |
C |
p.
|
artikel
|
| 24 |
SANS and neutron diffraction study of ausformed EUROFER97/2 ferritic/martensitic steel
|
Coppola, R.
|
|
|
24 |
C |
p.
|
artikel
|
| 25 |
Simulation of the first wall shielding during upward VDE in DEMO
|
Pestchanyi, Sergey
|
|
|
24 |
C |
p.
|
artikel
|
| 26 |
Small-angle neutron scattering (SANS) characterization of 13.5 Cr oxide dispersion strengthened ferritic steel for fusion applications
|
Coppola, R.
|
|
|
24 |
C |
p.
|
artikel
|
| 27 |
The size dependence of microstructure and hardness on the MA powders for the MA-HIP processed Cu-Y2O3 dispersion-strengthened alloys
|
Ma, Bing
|
|
|
24 |
C |
p.
|
artikel
|
| 28 |
Tungsten nitride as tritium permeation barrier
|
Houben, A.
|
|
|
24 |
C |
p.
|
artikel
|
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