ITER grade stainless steel (SS) 316L(N)-IG was tested in QSPA-T (photons) and JUDITH (electrons) under heat loads relevant to those expected from photon radiation on the ITER diagnostic first wall (DFW) during disruptions mitigated by massive gas injection. Repeated pulses slightly above the melting threshold eventually lead to a regular, “corrugated” SS surface, with hills and valleys spaced by 1–2 mm. The negligible mass loss observed after the heat pulses indicates that hill growth (growth rate of ∼1–2 μm per pulse) and SS plate thinning in the valleys is a result of melt-layer redistribution. A Similar behavior is observed on SS samples exposed in QSPA-T (pulse length 0.5 ms) and JUDITH (pulse length ⩽ 3.0 ms) at the same heat flux fact...
Combined thermal shock and steady-state heat loads (SSHLs) can have an impact on divertor materials ...
Metallic mirrors are foreseen in ITER diagnostic systems as optical elements directly viewing the pl...
The experimental fusion reactor ITER will apply beryllium as first wall armor material. In present f...
PFMs (Plasma-facing materials: ITER grade stainless steel, beryllium, and ferritic–martensitic steel...
Targets made of ITER-grade 316L(N)-IG stainless steel and Russian-grade 12Cr18Ni10Ti stainless steel...
To investigate the performance of stainless steel under transient thermal events, such as photon pul...
The paper presents the main results of numerous experiments carried out over the past 10 years at QS...
Tungsten has been chosen as the main candidate for plasma facing components (PFCs) in the magnetic c...
Cracking thresholds and crack patterns in tungsten targets after repetitive ITER-like edge localized...
In the dose and temperature range anticipated for ITER, austenitic stainless steels exhibit signific...
A relatively clean, safe, and promising solution to cover the globally increasing energy demand but ...
Experiments on the effect of fast heat loads on the surface of tungsten were carried out on the BETA...
A relatively clean, safe, and promising solution to cover the globally increasing energy demand but ...
Disk compact specimens of candidate materials for first wall/blanket structures in ITER have been ir...
The experimental fusion reactor ITER will apply beryllium as first wall armor material. In present f...
Combined thermal shock and steady-state heat loads (SSHLs) can have an impact on divertor materials ...
Metallic mirrors are foreseen in ITER diagnostic systems as optical elements directly viewing the pl...
The experimental fusion reactor ITER will apply beryllium as first wall armor material. In present f...
PFMs (Plasma-facing materials: ITER grade stainless steel, beryllium, and ferritic–martensitic steel...
Targets made of ITER-grade 316L(N)-IG stainless steel and Russian-grade 12Cr18Ni10Ti stainless steel...
To investigate the performance of stainless steel under transient thermal events, such as photon pul...
The paper presents the main results of numerous experiments carried out over the past 10 years at QS...
Tungsten has been chosen as the main candidate for plasma facing components (PFCs) in the magnetic c...
Cracking thresholds and crack patterns in tungsten targets after repetitive ITER-like edge localized...
In the dose and temperature range anticipated for ITER, austenitic stainless steels exhibit signific...
A relatively clean, safe, and promising solution to cover the globally increasing energy demand but ...
Experiments on the effect of fast heat loads on the surface of tungsten were carried out on the BETA...
A relatively clean, safe, and promising solution to cover the globally increasing energy demand but ...
Disk compact specimens of candidate materials for first wall/blanket structures in ITER have been ir...
The experimental fusion reactor ITER will apply beryllium as first wall armor material. In present f...
Combined thermal shock and steady-state heat loads (SSHLs) can have an impact on divertor materials ...
Metallic mirrors are foreseen in ITER diagnostic systems as optical elements directly viewing the pl...
The experimental fusion reactor ITER will apply beryllium as first wall armor material. In present f...