INGENIERÍA ENERGÉTICA
Saila
Gabriel
Pedroche Sánchez
Gabriel Pedroche Sánchez-rekin lankidetzan egindako argitalpenak (14)
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
2022
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Development of radiation sources for nuclear analysis beyond ITER bio-shield: SRC-UNED code
Computer Physics Communications, Vol. 275
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Shielding conceptual designs of ITER TCP ports to protect electronics
Fusion Engineering and Design, Vol. 176
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
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Nuclear data for D1SUNED for the study of ITER planned in-situ maintenance dose scenarios
Fusion Engineering and Design, Vol. 170
2020
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D1SUNED system for the determination of decay photon related quantities
Fusion Engineering and Design, Vol. 151
2019
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Nuclear analysis of the ITER torus cryopumps
Nuclear Fusion, Vol. 59, Núm. 10
2018
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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