Aljǎz
Koľsek
Publicaciones en las que colabora con Aljǎz Koľsek (15)
2024
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Corrigendum to “Total Ionizing Dose Estimation of ITER Upper Port Remote Handling Equipment” [Fusion Engineering and Design volume 202 (2024) 114359] (Fusion Engineering and Design (2024) 202, (S0920379624002126), (10.1016/j.fusengdes.2024.114359))
Fusion Engineering and Design
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ITER full model in MCNP for radiation safety demonstration
Nature Communications , Vol. 15, Núm. 1
2021
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A full and heterogeneous model of the ITER tokamak for comprehensive nuclear analyses
Nature Energy, Vol. 6, Núm. 2, pp. 150-157
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Improved radiation shielding analysis considering vector calculus
International Journal of Energy Research, Vol. 45, Núm. 8, pp. 11904-11915
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Integral modelling of the ITER cooling water systems radiation source for applications outside of the Bio-shield
Fusion Engineering and Design, Vol. 171
2019
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Nuclear analysis of the ITER torus cryopumps
Nuclear Fusion, Vol. 59, Núm. 10
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Shielding proposal to mitigate the PFC #2 heating due to 16N decay photon radiation from the activated cooling water
Fusion Engineering and Design, Vol. 148
2018
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MCNP model of the ITER Tokamak Complex
Fusion Engineering and Design, Vol. 136, pp. 859-863
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Scoping studies of shielding to reduce the shutdown dose rates in the ITER ports
Nuclear Fusion, Vol. 58, Núm. 7
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Shutdown dose rate mitigation in the ITER upper ports
Fusion Engineering and Design, Vol. 136, pp. 228-232
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The use of the long modular diagnostics shield module to mitigate shutdown dose rates in the ITER diagnostics equatorial ports
Nuclear Fusion, Vol. 58, Núm. 5
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Update in the nuclear responses of the European TBMs for ITER during operation and shutdown
Fusion Engineering and Design, Vol. 134, pp. 92-96
2017
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How to reduce shutdown dose rates in ITER diagnostics quatorial ports
Transactions of the American Nuclear Society
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Overview of nuclear integration activities for mitigation of radiation loads to ITER superconducting magnets
Transactions of the American Nuclear Society
2014
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Feasibility study of installing a thermal to 14 mev neutron converter into a research nuclear reactor
Proceedings of the International Conference on Physics of Reactors, PHYSOR 2014