A full tungsten divertor for ITER: Physics issues and design status
By R. Pitts, S. Carpentier, F. Escourbiac, T. Hirai, V. Komarov, S. Lisgo, A. Kukushkin, Alberto Loarte, M. Merola, A. S. Naik and 4 more. 2013
732 citations recorded by the source corpus.
Subfields: Materials Chemistry, Nuclear and High Energy Physics
View Paper: https://www.semanticscholar.org/paper/dd8f47e0822d4de04d91da00e3546900380777ed
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In Materials Chemistry
In Nuclear and High Energy Physics
Citations in the corpus
- European divertor target concepts for DEMO: Design rationales and high heat flux performance (2018, background): “The divertor target plates are the most thermally loaded in-vessel components in a fusion reactor where high heat fluxes (HHFs) are produced on the plasma-facing components (PFCs) by intense plasma bombardment, radiation and nuclear heating by neutron irradiation [4].”
- A new experimental classification of divertor detachment in ASDEX Upgrade (2013, unknown): “being detached or partially detached [1, 2].”
- Tungsten ‘fuzz’ growth re-examined: the dependence on ion fluence in non-erosive and erosive helium plasma (2015, background): “36 ×10−38 m(4), which is a fair assumption given the hottest parts of the W divertor region are expected to be 1000 - 1400 K [35], this gives xeq = 0.”