Damage studies on tungsten due to helium ion irradiation
NJ Dutta, N Buzarbaruah, SR Mohanty - Journal of Nuclear Materials, 2014 - Elsevier
Energetic and high fluence helium ions emitted in a plasma focus device have been used
successfully to study the radiation induced damage on tungsten. The reference and …
successfully to study the radiation induced damage on tungsten. The reference and …
Novel test-bed facility for PSI issues in fusion reactor conditions on the base of next generation QSPA plasma accelerator
IE Garkusha, VV Chebotarev, SS Herashchenko… - Nuclear …, 2017 - iopscience.iop.org
In this report a concept of a new generation QSPA with external B-field up to 2 T has been
discussed. A novel test-bed facility, which was recently constructed in Kharkov IPP NSC …
discussed. A novel test-bed facility, which was recently constructed in Kharkov IPP NSC …
Behaviour of tungsten alloy with iron and nickel under repeated high temperature plasma pulses
The changes of the structure and properties of a dual phase tungsten (W) alloy (with either
3% or 5% of an added mixture of Fe and Ni) are investigated after irradiation with powerful …
3% or 5% of an added mixture of Fe and Ni) are investigated after irradiation with powerful …
Preparation of spherical tungsten powder with uniform distribution of lanthania by plasma spheroidization
D Wang, Z Hao, P Wang, R Ma, Y Shu, J He - International Journal of …, 2023 - Elsevier
The high ductile-brittle transition temperature of tungsten (W) makes it prone to crack during
additive manufacturing. Incorporating lanthania (La 2 O 3) to tungsten had been proven to …
additive manufacturing. Incorporating lanthania (La 2 O 3) to tungsten had been proven to …
Effects of fusion relevant transient energetic radiation, plasma and thermal load on PLANSEE double forged tungsten samples in a low-energy plasma focus device
Tungsten is the leading candidate for plasma facing component (PFC) material for
thermonuclear fusion reactors and various efforts are ongoing to evaluate its performance or …
thermonuclear fusion reactors and various efforts are ongoing to evaluate its performance or …
Morphology evolution of La2O3 and crack characteristic in W–La2O3 alloy under transient heat loading
X Zhang, Q Yan - Journal of Nuclear Materials, 2014 - Elsevier
Thermal shock tests were performed on W–La 2 O 3 specimens by an electron beam to
investigate the morphology evolution of La 2 O 3 and crack characteristics. Cracks appeared …
investigate the morphology evolution of La 2 O 3 and crack characteristics. Cracks appeared …
The experimental and theoretical investigations of damage development and distribution in double-forged tungsten under plasma irradiation-initiated extreme heat …
B Väli, T Laas, J Paju, V Shirokova, M Paduch… - Nukleonika, 2016 - sciendo.com
The influence of extreme heat loads, as produced by a multiple pulses of non-homogeneous
flow of slow plasma (0.1–1 keV) and fast ions (100 keV), on double-forged tungsten (DFW) …
flow of slow plasma (0.1–1 keV) and fast ions (100 keV), on double-forged tungsten (DFW) …
Impact of pulsed deuterium plasma irradiation on dual-phase tungsten alloys
S Tõkke, T Laas, J Priimets, V Mikli… - Fusion Engineering and …, 2021 - Elsevier
The morphological and structural changes of two different dual-phase tungsten alloy (either
3% or 5% of an added mixture of Fe and Ni) are investigated after deuterium plasma …
3% or 5% of an added mixture of Fe and Ni) are investigated after deuterium plasma …
Multifractal analysis of high-temperature plasma irradiated tungsten surfaces
In this research, the irregular surface structure of 15 pure tungsten specimens that are
irradiated respectively with 20, 40, 60, 80, and 100 shots of high-temperature deuterium …
irradiated respectively with 20, 40, 60, 80, and 100 shots of high-temperature deuterium …
Application of dense plasma focus devices and lasers in the radiation material sciences for the goals of inertial fusion beyond ignition
VA Gribkov, IV Borovitskaya, EV Demina… - Matter and Radiation …, 2020 - pubs.aip.org
Specimens of materials for prospective use in chambers of nuclear fusion reactors with
inertial plasma confinement, namely, W, ODS steels, Eurofer 97 steel, a number of ceramics …
inertial plasma confinement, namely, W, ODS steels, Eurofer 97 steel, a number of ceramics …