Zobrazeno 1 - 10
of 64
pro vyhledávání: '"K. Herschbach"'
Publikováno v:
Journal of Nuclear Materials. 203:233-248
A pressurized tube experiment was carried out to determine swelling and in-pile creep of a series of model plain Fe-15Cr-15Ni stainless steels and of different heats of the commercial German steel DIN 1.4970. Special attention was paid to the influen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::54c79f8e3d3a47550c7ea848f9ce0dfd
https://doi.org/10.1016/0022-3115(93)90380-h
https://doi.org/10.1016/0022-3115(93)90380-h
From a pressurized capsules irradiation experiment RIPCEX I in-pile creep deformation data were obtained by subtracting the strains due to swelling from the total deformations. The remaining creep strains may be explained as the sum of two deformatio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eca77de94d65d85a844cff7e33f672b4
https://doi.org/10.1520/stp34337s
https://doi.org/10.1520/stp34337s
Autor:
H.-J. Bergmann, K. Herschbach
Publikováno v:
Journal of Nuclear Materials. 175:143-146
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::48ba2a54d80b295392a84037d02cc8b5
https://doi.org/10.1016/0022-3115(90)90281-q
https://doi.org/10.1016/0022-3115(90)90281-q
Autor:
H. Renner, K. Herschbach, J.E. Vetter, H. Greuner, F. Kerl, W. Bitter, W. Maurer, J. Kisslinger
For the HELIAS stellarator W7X design studies of the divertor are presented. Under stationary conditions for energy and particle exhaust high local load to target plates with values up to 10 MW/m 2 is expected. The modular target area and the associa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e5980a391d90919e2531722de120411a
https://doi.org/10.1016/b978-0-444-82220-8.50049-2
https://doi.org/10.1016/b978-0-444-82220-8.50049-2
Autor:
G. Federici, G. Janeschitz, K.J. Dietz, J.E. Vetter, K. Herschbach, E. Martin, R. Tivey, S. Chiocchio, W. Maurer
This paper describes the mechanical, thermo-hydraulic, manufacturing, installation and remote maintenance aspects of the design of divertor cassettes proposed for the ITER EDA. Emphasis is given to the use of manufacturing techniques that have been d
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a18914157164fbd87a0e69fede1f59c3
https://doi.org/10.1016/b978-0-444-82220-8.50053-4
https://doi.org/10.1016/b978-0-444-82220-8.50053-4
Autor:
G. Janeschitz, A. Antipenkov, E. Martin, S. Chiocchio, W. Maurer, G. Federici, K. Herschbach, J.E. Vetter
This paper describes the mechanical, thermo-hydraulic, manufacturing, installation and remote maintenance aspects of the design of divertor baffles proposed for the ITER EDA.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8dfff9a53faf653fc329f5cf6c27ef37
https://doi.org/10.1016/b978-0-444-82220-8.50044-3
https://doi.org/10.1016/b978-0-444-82220-8.50044-3
Autor:
K. Herschbach, T. Iizuka, K. Shimizu, D. Williamson, J.E. Vetter, K. Ioki, W. Maurer, G. Johnson
Major functional requirements for the vacuum vessel are to provide the first safety barrier and to support electromagnetic loads due to plasma disruptions and vertical displacement events, and to withstand plausible accidents without losing confineme
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::045fa2e2ed498ecc8db8ecb974eaf2c2
https://doi.org/10.1016/b978-0-444-82220-8.50056-x
https://doi.org/10.1016/b978-0-444-82220-8.50056-x
In the frame of high heat flux development for plasma facing components, CEA has designed, fabricated and tested over twenty specimens, with some of them for the NET divertor application. Several CFC and copper grades have been used with flat tile or
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4ff88fabe520ddac3013e88e9f12d214
https://doi.org/10.1016/b978-0-444-82220-8.50077-7
https://doi.org/10.1016/b978-0-444-82220-8.50077-7
Autor:
G. Janeschitz, W. Maurer, G. Federici, K. Herschbach, K.J. Dietz, V. Barabash, R. Matera, S. Tanaka, J. E. Vetter
The description of current status with the choice of materials for ITER plasma facing components is presented. The main problem with lifetime of divertor elements is the particle and energy-induced erosion of armour materials. A solution for the firs
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::60daf5fe108e90801def4a4ac9f0c489
https://doi.org/10.1016/b978-0-444-82220-8.50028-5
https://doi.org/10.1016/b978-0-444-82220-8.50028-5