Zobrazeno 1 - 10
of 43
pro vyhledávání: '"G. Messemer"'
Autor:
L. Dörr, G. Laffont, Andrea Ciampichetti, I. Platnieks, M. Ilic, L. Bühler, J.F. Freibergs, G. Rampal, A. Aiello, Bradut-Eugen Ghidersa, David Demange, G. Messemer
Publikováno v:
Fusion Engineering and Design. 85:2012-2021
European test blanket modules (TBM) for both European blanket concepts, namely the Helium Cooled Lithium Lead (HCLL) and the Helium Cooled Pebble Bed (HCPB), and their auxiliary systems have been designed in the last years. This paper presents the ex
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c93eb0053fdf05f81458bab5baada291
https://doi.org/10.1016/j.fusengdes.2010.07.007
https://doi.org/10.1016/j.fusengdes.2010.07.007
Publikováno v:
Fusion Engineering and Design. 84:974-978
HELOKA experimental facility, aimed to test the test blanket modules (TBM) mock-ups and prototypes, is under construction at the Research Centre Karlsruhe. HELOKA is an “8-shape” helium loop (HL), which feeds the TBM test section with helium (1.4
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eab0dd0f1c6adfa36574bfd292d90dd1
https://doi.org/10.1016/j.fusengdes.2008.12.046
https://doi.org/10.1016/j.fusengdes.2008.12.046
Publikováno v:
Fusion Engineering and Design. 82:2812-2816
A helium-cooled divertor concept for future power plants to be build after ITER is investigated at the Forschungszentrum Karlsruhe [1] . Simulations by computational fluid dynamics (CFD) programs show that the divertor is capable of removing a heat l
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::aee5f1b636ceecb8bd9a91581ce3360c
https://doi.org/10.1016/j.fusengdes.2007.03.049
https://doi.org/10.1016/j.fusengdes.2007.03.049
Autor:
G. Messemer, R. Krieg, T. Jordan, B Göller, N. Prothmann, E. Stratmanns, G Hailfinger, B. Dolensky
Publikováno v:
Nuclear Engineering and Design. 223:237-253
The load carrying capacity of the pressure vessel head to withstand a postulated in-vessel steam explosion has been investigated. Former results have been confirmed and extended. For a quite conservative reference case the mechanical energy release w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2f20ff213ed4ee5b482364d55cb51da7
https://doi.org/10.1016/s0029-5493(03)00042-6
https://doi.org/10.1016/s0029-5493(03)00042-6
Autor:
G. Messemer, E. Stratmanns, H Benz, T. Malmberg, B Göller, G Hailfinger, B. Dolensky, W Ratajczak, O. Jonatzke, R. Krieg, G. Vorberg
Publikováno v:
Nuclear Engineering and Design. 202:179-196
The load carrying capacity of the pressure vessel head to withstand an in-vessel steam explosion is investigated. Firstly, as a key problem, the impact of molten core material against the vessel head is studied by model experiments scaled down 1:10.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c3a24d6614d6795cd3e6577e086aaa28
https://doi.org/10.1016/s0029-5493(00)00357-5
https://doi.org/10.1016/s0029-5493(00)00357-5
Publikováno v:
Nuclear Technology. 111:369-385
The most severe consequence of a pressurized water reactor in-vessel steam explosion is a molten fuel slug impact against the head of the reactor pressure vessel that could cause a failure of this head and lead to missiles endangering the reactor con
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a3c702c060ed1c049a9637b2c9770019
https://doi.org/10.13182/nt95-a15867
https://doi.org/10.13182/nt95-a15867
Publikováno v:
Kerntechnik. 59:178-192
A steam explosion in a reactor pressure vessel could cause a strong molten fuel slug impact of the vessel head, whose failure would question the integrity of the reactor containment. The capacity of a typical pressurized water reactor vessel head to
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::abbafe6a8f07ca878e56b620d8edc1e3
https://doi.org/10.1515/kern-1994-594-512
https://doi.org/10.1515/kern-1994-594-512
Publikováno v:
ICRA
A large-range (22-m) heavy-payload (1.4-ton) redundant manipulator (EMIR) for outdoor applications is presented. The authors introduce the kinematics of the robot and the basic features of the control system. The latter includes planning modules as w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::580cddc7d1467d08add85d7154f44bed
https://doi.org/10.1109/robot.1989.100018
https://doi.org/10.1109/robot.1989.100018
Publikováno v:
Nuclear Engineering and Design. 100:205-219
During a hypothetical core melt accident the pressure inside the containment will gradually increase until the design limits are exceeded and finally failure of the containment occurs. The investigations showed that failure of the containment shell i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eecd92bf4bb51192fb976573814e7f2d
https://doi.org/10.1016/0029-5493(87)90043-4
https://doi.org/10.1016/0029-5493(87)90043-4
Publikováno v:
Nuclear Engineering and Design. 82:77-87
The investigations will deal with the mechanical behavior of a free standing spherical containment shell built for the latest type of a German pressurized water reactor. The diameter of the containment shell is 56 m. The wall thickness is 38 mm. The
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::25cbecd3ca73b826195b438982ae9b0a
https://doi.org/10.1016/0029-5493(84)90268-1
https://doi.org/10.1016/0029-5493(84)90268-1