共 25 条
- [1] Norajitra P, Giniyatulin R, Kuznetsov V, Et al., He-cooled divertor for DEMO: status of development and HHF tests [J], Fusion Engineering and Design, 85, 10 – 12, pp. 2251-2256, (2010)
- [2] Norajitra P, Giniyatulin R, Holstein N, Et al., Status of He-cooled divertor development for DEMO[J], Fusion Engineering and Design, pp. 307-311, (2005)
- [3] Rodig M, Duwe R, Kuhnlein W, Et al., Testing of actively cooled high heat flux mock-ups[J], Journal of Nuclear Materials, 258, pp. 967-971, (1998)
- [4] Ge C C, Zhou Z J, Song S X, Et al., Progress of research on plasma facing materials in University of Science and Technology Beijing[J], Journal of Nuclear Materials, 363, pp. 1211-1215, (2007)
- [5] Weber T, Aktaa J., Numerical assessment of functionally graded tungsten/steel joints for divertor applications[J], Fusion Engineering and Design, 86, 2 – 3, pp. 220-226, (2011)
- [6] Simonovski I, Koncar B, Cizelj L., Thermo-mechanical analysis of a DEMO divertor cooling finger under the EFREMOV test conditions[J], Fusion Engineering and Design, 85, 1, pp. 130-137, (2010)
- [7] Klein F, Wegener T, Litnovsky A, Et al., Oxidation resistance of bulk plasma-facing tungsten alloys[J], Nuclear Materials and Energy, 15, pp. 226-231, (2018)
- [8] Bolt H, Barabash V, Krauss W, Et al., Materials for the plasma-facing components of fusion reactors[J], Journal of Nuclear Materials, 329, pp. 66-73, (2004)
- [9] Gruber O, Sips A C C, Dux R, Et al., Compatibility of ITER scenarios with full tungsten wall in ASDEX Upgrade, Nuclear Fusion, 49, 11, (2009)
- [10] Davis J W, Slattery K T, Driemeyer D E, Et al., Use of tungsten coating on iter plasma facing components[J], Journal of Nuclear Materials, pp. 604-608, (1996)