Fuel inventory and material migration of JET main chamber plasma facing components compared over three operational periods
A Widdowson, S Aleiferis, E Alves, L Avotina… - Physica …, 2020 - iopscience.iop.org
Fuel retention and material migration results from JET ITER-like wall beryllium limiter tiles
are presented for three operating periods. Ion beam analysis results support the general …
are presented for three operating periods. Ion beam analysis results support the general …
LIBS investigation of metals suitable for plasma-facing components: Characteristics and comparison of picosecond and nanosecond regimes
AM Roldan, V Dwivedi, M Pisarčík, M Veis… - Fusion Engineering and …, 2021 - Elsevier
For ITER and other future fusion devices, tungsten (W) and its alloys are primary candidates
for the first wall in divertor, and molybdenum (Mo) will be used as the background material …
for the first wall in divertor, and molybdenum (Mo) will be used as the background material …
Fuel desorption from JET-ILW materials: assessment of analytical approach and identification of sources of uncertainty and discrepancy
Y Zayachuk, I Jepu, M Zlobinski, C Porosnicu… - Nuclear …, 2023 - iopscience.iop.org
This work was carried out to identify sources of errors, uncertainties and discrepancies in
studies of fuel retention in wall components from the JET tokamak using methods based on …
studies of fuel retention in wall components from the JET tokamak using methods based on …
[HTML][HTML] Global distribution of tritium in JET with the ITER-like wall
SE Lee, Y Hatano, M Tokitani, S Masuzaki… - Nuclear Materials and …, 2021 - Elsevier
Nondestructive analysis of tritium (T) distribution was performed by means of imaging plate
technique on specimens cut from the Be limiters, W-coated carbon tiles and bulk W lamellae …
technique on specimens cut from the Be limiters, W-coated carbon tiles and bulk W lamellae …
[HTML][HTML] Tritium retention in plasma facing materials of JET ITER-Like-Wall retrieved from the vacuum vessel in 2012 (ILW1), 2014 (ILW2) and 2016 (ILW3)
E Pajuste, G Kizane, L Avotina, A Vitins… - Nuclear Materials and …, 2021 - Elsevier
Abstract ITER-Like-Wall (ILW) project has been carried out at Joint European Torus (JET) to
test plasma facing materials relevant to International Thermonuclear Experimental Reactor …
test plasma facing materials relevant to International Thermonuclear Experimental Reactor …
[HTML][HTML] Determination of Tritium-Helium-3 differential cross-section in the energy range between 0.6 MeV and 3.3 MeV for tritium depth profiling in solids
S Markelj, A Cvetinović, M Lipoglavšek… - Nuclear Materials and …, 2024 - Elsevier
The differential cross-section for the 3 He+ 3 H nuclear reaction was measured in a thin
tritiated PdTi film that was deposited on a Si wafer. The sample was loaded with 3 H 2 gas at …
tritiated PdTi film that was deposited on a Si wafer. The sample was loaded with 3 H 2 gas at …
[HTML][HTML] Comparison of the structure of the plasma-facing surface and tritium accumulation in beryllium tiles from JET ILW campaigns 2011–2012 and 2013–2014
E Pajuste, G Kizane, I Igaune, L Avotina… - Nuclear Materials and …, 2019 - Elsevier
In this study, beryllium tiles from Joint European Torus (JET) vacuum vessel wall were
analysed and compared regarding their position in the vacuum vessel and differences in the …
analysed and compared regarding their position in the vacuum vessel and differences in the …
Hydrogen isotopes separation validation of frontal displacement chromatography for various compositions of feed gas and tritium extraction simulation for TBM
X Deng, D Luo, C Qin, D Meng, T Tang… - international journal of …, 2018 - Elsevier
Based on the previous study in frontal displacement chromatography (FDC) packed with Pd-
Al 2 O 3, three groups of separation tests were carried out to verify the separation …
Al 2 O 3, three groups of separation tests were carried out to verify the separation …
Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry
SE Lee, Y Hatano, M Hara, S Masuzaki… - Fusion Engineering and …, 2020 - Elsevier
Tritium (T) distribution on the plasma-facing surfaces (PFSs) and inside castellation of Be
limiter tiles from the JET tokamak with the ITER-like wall (ILW) was analyzed using imaging …
limiter tiles from the JET tokamak with the ITER-like wall (ILW) was analyzed using imaging …
Recommended electron-impact excitation and ionization cross sections for Be I
Analytic fits to the recommended electron-impact excitation and ionization cross sections for
Be I are presented. The lowest 19 terms of configurations 2 snl (n≤ 4) and 2 p 2 terms below …
Be I are presented. The lowest 19 terms of configurations 2 snl (n≤ 4) and 2 p 2 terms below …