Zobrazeno 1 - 10
of 2 189
pro vyhledávání: '"B, Spilker"'
Publikováno v:
Quality of Life Research, 1997 Jan 01. 6(1), 97-98.
Externí odkaz:
https://www.jstor.org/stable/4035290
Autor:
Elbourne, Diana
Publikováno v:
Journal of Epidemiology and Community Health (1979-), 1992 Oct 01. 46(5), 547-547.
Externí odkaz:
https://www.jstor.org/stable/25567611
Autor:
M. Zlobinski, G. Sergienko, Y. Martynova, D. Matveev, B. Unterberg, S. Brezinsek, B. Spilker, D. Nicolai, M. Rasinski, S. Möller, Ch. Linsmeier, C.P. Lungu, C. Porosnicu, P. Dinca, G. De Temmerman
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss , Pp 503-509 (2019)
For the development of the tritium monitoring system in ITER the hydrogen isotope release by Laser-Induced Desorption (LID) from Be layers is studied to determine the laser parameters for a high desorption efficiency while minimising dust production
Externí odkaz:
https://doaj.org/article/5220f7ccd76948959744dbb21a39cd86
Publikováno v:
Nuclear Materials and Energy, Vol 18, Iss , Pp 291-296 (2019)
The plasma facing first wall in ITER will be armored with beryllium. During operation, the armor has to sustain direct plasma contact during the start-up and ramp-down of the plasma. On top, transient thermal loads originating from a variety of plasm
Externí odkaz:
https://doaj.org/article/d4beeebca84649cb97cfe2afab5e951e
Autor:
Stephen McKenna
Publikováno v:
Journal of Community & Applied Social Psychology. 7:425-426
Autor:
Anthony R. Scialli
Publikováno v:
Reproductive Toxicology. 9:589-590
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 1184-1188 (2017)
The experimental fusion reactor ITER will apply beryllium as first wall armor material. In present fusion experiments, e.g. ASDEX Upgrade, it has been detected that up to 25% of the plasma energy loss is deposited in non divertor regions during edge
Externí odkaz:
https://doaj.org/article/e77b0db9e22d4e478aeb0ac01b0f3fba
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 98-103 (2016)
Simulation of beryllium cracking under action of multiple severe surface heatings has been performed using the PEGASUS-3D code and verified by experiments in the JUDITH 1 facility. Analysis of the results has revealed beryllium thermo conductivity de
Externí odkaz:
https://doaj.org/article/b9eacb48e1f240d5b2cce69036bc4647
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 145-152 (2016)
Massive gas injections (MGIs) will be used in ITER to mitigate the strong damaging effect of full performance plasma disruptions on the plasma facing components. The MGI method transforms the stored plasma energy to radiation that is spread across th
Externí odkaz:
https://doaj.org/article/ac862e963d0442efaa74e9097928995e
Autor:
Christian Linsmeier, M. Zlobinski, S. Brezinsek, Gerald Pintsuk, Yulia Martynova, A. Huber, Jörg Thomas, Andreas Bürger, B. Spilker, Karsten Dominiczak, Dirk Nicolai, H. G. Esser, Alexis Terra, Gennady Sergienko, B. Unterberg, B. Schweer, Michaele Freisinger
Publikováno v:
Fusion Engineering and Design
In fusion devices, the retention of the fusion fuel deuterium (D) and tritium (T) in plasma-facing components (PFCs) is a major concern. Measurement of their hydrogen isotope content gives insight into the retention physics. In FREDIS, two methods of