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| Hauptseite > Publikationsdatenbank > Assessment of beryllium as a plasma-facing material for next step fusion devices > print |
| Hauptseite > Publikationsdatenbank > Assessment of beryllium as a plasma-facing material for next step fusion devices > print |
| 001 | 29352 | ||
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| 100 | 1 | _ | |0 P:(DE-Juel1)VDB3005 |a Lodato, Alessandra |b 0 |e Corresponding author |u FZJ |
| 245 | _ | _ | |a Assessment of beryllium as a plasma-facing material for next step fusion devices |
| 260 | _ | _ | |a Jülich |b Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag |c 2001 |
| 300 | _ | _ | |a 158 p. |
| 336 | 7 | _ | |0 PUB:(DE-HGF)11 |2 PUB:(DE-HGF) |a Dissertation / PhD Thesis |
| 336 | 7 | _ | |0 PUB:(DE-HGF)3 |2 PUB:(DE-HGF) |a Book |
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| 336 | 7 | _ | |2 BibTeX |a PHDTHESIS |
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| 490 | 0 | _ | |0 PERI:(DE-600)2414853-2 |8 424 |a Berichte des Forschungszentrums Jülich |v 3908 |x 0944-2952 |
| 500 | _ | _ | |a Record converted from VDB: 12.11.2012 |
| 502 | _ | _ | |a Aachen, Techn. Hochsch., Diss, 2001 |b Dr. (FH) |c Techn. Hochsch. Aachen |d 2001 |
| 520 | _ | _ | |a The selection of the armour materials for the plasma facing components (PFC) was one of the important challenging problems in the design of the International Thermonuclear Experimental Reactor (ITER). The working conditions of the plasma facing materials (PFM) are very complex. During normal operation they are subjected to high cyclic heat fluxes which originate thermal fatigue and simultaneously to high particle fluxes which produce erosion. During off normal operations the PFMs may suffer severe thermal shocks caused by plasma disruptions and by vertical displacement events of the plasma. Beside carbon material and tungsten, beryllium will play an important role as PFM in ITER. For the construction of PFCs the beryllium tiles have to be attached to a heat sink of copper. Several techniques of joining such as brazing and hot isostatic pressing are under consideration. During the operation of HER the PFMs will suffer irradiation with 14 MeV neutrons generated in the fusion process. This irradiation will affect the thermal and mechanical properties of beryllium and beryllium-copper joints. To validate the choice of the reference beryllium grade and Be/Cu joint, there is a need to investigate their behaviour under combined exposure to thermal loading and neutron irradiation. To investigate the materials degradation processes, thermal shock samples from different beryllium grades, actively cooled Be/CuCrZr mock-ups and mechanical test samples have been neutron irradiated in the High Flux Reactor at Petten, The Netherlands. In the present work the experimental assessment of neutron irradiation effects on Be material has been carried out by performing thermal shock tests on beryllium samples of different grades. The thermal shock behaviour of the different beryllium grades before and after neutron irradiation has been compared. Furthermore, the experimental verification of neutron damage on Be/Cu joints has been achieved by performing thermal fatigue tests on beryllium-copper mock-ups. The heat removal efficiency and the thermal fatigue behaviour of mock-ups with CuMnSnCe braze and with InCuSil braze before and after neutron irradiation have been compared. |
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