Materials Science and Technology 2006
DOI: 10.1002/9783527603978.mst0114
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Fusion Reactor Materials

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Cited by 5 publications
(9 citation statements)
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“…(2) The microstructure observation showed that more voids were induced by proton irradiation than by neutron irradiation because the protons tended to remain on the surface, but a higher number density and a larger size of dislocation loops were given in neutron-irradiated samples. (3) Irradiation hardening was induced for each sample even in W-26Re where no voids and dislocation loops were observed.…”
Section: Discussionmentioning
confidence: 99%
See 1 more Smart Citation
“…(2) The microstructure observation showed that more voids were induced by proton irradiation than by neutron irradiation because the protons tended to remain on the surface, but a higher number density and a larger size of dislocation loops were given in neutron-irradiated samples. (3) Irradiation hardening was induced for each sample even in W-26Re where no voids and dislocation loops were observed.…”
Section: Discussionmentioning
confidence: 99%
“…Tungsten (W) has been considered as one of the candidate materials for plasma-facing components (PFCs) of the fusion reactor [1][2][3]. Under 14 MeV-neutron irradiation conditions in fusion reactors, large amounts of solid transmutation products, mainly including rhenium (Re) and osmium (Os), will be produced from the transmutation actions of W [4,5], and this reaction will cause the sigma phase formation.…”
Section: Introductionmentioning
confidence: 99%
“…To summarise, ferritic steels are likely candidates in the design of fusion reactors and if implemented will be exposed to 14 MeV neutrons and total irradiation doses of some ≈ 200 dpa [4]. A great deal of research is underway to study the consequences of such an environment on the properties of the steels, but because appropriate experimental facilities do not exist, much of the work is theoretical.…”
Section: Reduced-activation Steelsmentioning
confidence: 99%
“…For instance several components of ITER will consist of various combinations of joints between armour materials and Cu alloys heat sinks, see [1][2][3]. The ceramic materials forming the joints are for example carbon-fiber-carbon (CFC), carbon-carbon (C/C) composites and silicon carbide (SiC).…”
Section: Introductionmentioning
confidence: 99%
“…The ceramic materials forming the joints are for example carbon-fiber-carbon (CFC), carbon-carbon (C/C) composites and silicon carbide (SiC). For CFC/ Cu joints several technologies have been developed and studied like active metal casting technology, which includes special laser pretreatment of the CFC surface followed by casting of pure Cu into CFC [3] or brazing with silver-free alloys such as CuMn and CuSiAlTi. In both cases wettability is a crucial problem.…”
Section: Introductionmentioning
confidence: 99%