Zobrazeno 1 - 10
of 48
pro vyhledávání: '"A.J. Magielsen"'
Autor:
B.T. Straathof, C. Ohms, E. D’Agata, O. Martin, T. Bakker, A.J. Magielsen, Z. Szaraz, P. ten Pierick, M. Kolluri
Publikováno v:
Journal of Nuclear Materials. 553:153036
Understanding the irradiation induced degradation of the reactor pressure vessel (RPV) steels at high fluences becomes more important in view of safe long term operation (LTO) of existing nuclear power plants. Specifically, the role of Ni, Mn and Si
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6d49332f8d8575d654cd5dea5f4cc49f
https://doi.org/10.1016/j.jnucmat.2021.153036
https://doi.org/10.1016/j.jnucmat.2021.153036
Autor:
A.J. Magielsen, M. Kolluri, G. Sevikyan, Varos G. Petrosyan, P. Hähner, Z. Szaraz, A. Kryukov
Publikováno v:
Journal of Nuclear Materials. 486:138-147
The integrity assessment of the Reactor Pressure Vessel (RPV) is essential for the safe and Long Term Operation (LTO) of a Nuclear Power Plant (NPP). Hardening and embrittlement of RPV caused by neutron irradiation and thermal ageing are main reasons
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c7989f2e5b5caaec041a86f01f82764c
https://doi.org/10.1016/j.jnucmat.2017.01.007
https://doi.org/10.1016/j.jnucmat.2017.01.007
Publikováno v:
Journal of Nuclear Materials. 448:139-143
This paper presents the results of the tritium permeation study in EUROFER97 carried out within the EXOTIC (EXtraction Of Tritium In Ceramics) irradiation experiment. In the EXOTIC 9/1 experiment, a pebble bed assembly containing Lithium Titanate (Li
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::12b509971bf2a2ec53d2d9b967cb3a87
https://doi.org/10.1016/j.jnucmat.2014.01.022
https://doi.org/10.1016/j.jnucmat.2014.01.022
Autor:
A.J. Magielsen, Pavel Vladimirov, A. Moeslang, V. Chakin, M.H.H. Kolb, M. Zmitko, H.-C. Schneider, Michael Klimenkov, R. Rolli, P. Kurinskiy, S. van Til
Publikováno v:
Journal of Nuclear Materials. 442:S483-S489
The current helium cooled pebble bed (HCPB) tritium breeding blanket concept for fusion reactors includes a bed of 1 mm diameter beryllium pebbles to act as a neutron multiplier. Beryllium pebbles, fabricated by the rotating electrode method, were ne
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8c4699e45b2aaa115ae0074753715944
https://doi.org/10.1016/j.jnucmat.2013.03.032
https://doi.org/10.1016/j.jnucmat.2013.03.032
Publikováno v:
Fusion Engineering and Design. 88:2918-2921
The reduced activation martensitic steel (RAFM) EUROFER is foreseen as a structural material in test breeder module (TBM) in ITER and breeder blanket in DEMO design. In a number of irradiation experiments conducted in high flux reactor (HFR) in Pette
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::48ea59c269b335acb6974a1eeeaaa9c9
https://doi.org/10.1016/j.fusengdes.2013.06.003
https://doi.org/10.1016/j.fusengdes.2013.06.003
Autor:
Gwendolijn Y. R. Schropp, Cock J.M. Heemskerk, B.S.Q. Elzendoorn, H.V. Hermes, Pieter T. Eendebak, A.J. Magielsen
Publikováno v:
Fusion Engineering and Design, 88, 1969-1972
Fusion Engineering and Design, 9-10, 88, 1969-1972
Fusion Engineering and Design, 9-10, 88, 1969-1972
Maintenance operations on ITER tokamak components will be largely performed by remote handling. In previous work it was shown that representative maintenance tasks could be performed significantly faster with direct visual feedback than with camera f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a21eb8771ba40edad2483a9d4be99440
https://doi.org/10.1016/j.fusengdes.2013.02.034
https://doi.org/10.1016/j.fusengdes.2013.02.034
Autor:
P. Kurinskiy, S. van Til, Pavel Vladimirov, R. Rolli, A. Moeslang, M. Zmitko, V. Chakin, A.J. Magielsen
Publikováno v:
Fusion Engineering and Design. 88:2309-2313
Small constrained beryllium pebble beds as well as unconstrained beryllium pebbles have been irradiated within HIDOBE-01 experiment at HFR, Petten, the Netherlands. Beryllium pebbles with 1 mm diameter produced by Rotating Electrode Method (REM) were
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::caf6fe577e4c311c137f92dec8973228
https://doi.org/10.1016/j.fusengdes.2013.04.034
https://doi.org/10.1016/j.fusengdes.2013.04.034
Publikováno v:
Fusion Engineering and Design. 88:2259-2263
In present fusion reactors designs, beryllium pebble beds are the prime candidate for use as neutron multiplier for the helium cooled pebble bed (HCPB) breeder blankets. In the 2 HIDOBE experiments ( HIgh DOse irradiation of BEryllium ; [1] ), perfor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::030f644140d1163e123fc7eecd5743e6
https://doi.org/10.1016/j.fusengdes.2013.04.047
https://doi.org/10.1016/j.fusengdes.2013.04.047
Publikováno v:
Fusion Engineering and Design. 87:885-889
The irradiation experiment Pebble Bed Assemblies (PBA) consists of four mock-up representations (test elements) of the EU Helium Cooled Pebble Bed (HCPB) concept. The four test elements contain a ceramic breeder pebble bed sandwiched between two bery
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9d536d1cb5391251acb855fd3a9bb168
https://doi.org/10.1016/j.fusengdes.2012.02.052
https://doi.org/10.1016/j.fusengdes.2012.02.052
Autor:
M. Zmitko, R. Knitter, R. Lässer, Yves Poitevin, J.B.J. Hegeman, J.-F. Salavy, A.J. Magielsen, Lorenzo Virgilio Boccaccini, Anton Möslang
Publikováno v:
Journal of Nuclear Materials. 417:678-683
Europe has developed two reference tritium breeder blankets concepts for a DEMO fusion reactor: the Helium-Cooled Lithium–Lead and the Helium-Cooled Pebble-Bed. Both will be tested in ITER under the form of Test Blanket Modules (TBMs). The paper re
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::082d26dc6fc6f9d41a9de61fb1cd7b0b
https://doi.org/10.1016/j.jnucmat.2011.02.009
https://doi.org/10.1016/j.jnucmat.2011.02.009