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Technology for Fusion (T4F)

List of publications on Fusion topics


D. Rapisarda, I. Fernandez, I. Palermo, M. Gonzalez, C. Moreno, A. Ibarra and E. Mas de les Valls. Conceptual Design of the EU-DCLL Dual Coolant Lithium Lead Equatorial Module (2016) IEEE Transactions on Plasma Science 44 (9), pp. 1603-1612

G. Aiello, C. Mistrangelo, L. Bühler, E. Mas de les Valls, J. Aubert, A. Li-Puma, D. Rapisarda and A. Del Nevo. MHD issues related to the use of lithium lead eutectic as breeding material for . blankets of fusion power plants (2015) Magnetohydrodynamics 51 (2), pp. 185-193

M. Perez, J. Freixa, E. Mas de les Valls, T. Sandeep, V. Chaudhari (Inst for Plasma Research). RELAP/SCDAPSIM/MOD4.0 Modification for Transient Accident Scenario of Test Blanket Modules Involving Helium Flows into Heavy Liquid Metal. NURETH-16 Chicago, Illinois, USA, Sep. 2015.

S. Smolentsev, S. Badia, R. Bhattacharyay, L. Bühler, L. Chen, Q. Huang, H-G. Jin, D. Krasnov, E-W. Lee, E. Mas de les Valls, C. Mistrangelo, R. Munipalli, M-J Ni, D. Pashkevich, A. Patel, G. Pulugundla, P. Satyamurthy, A. Snegirev, V. Sviridov, P. Swain, T. Zhou and O. Zikanov. An approach to verification and validation of MHD codes for fusion applications (2014) Fusion Engineering and Design 100, pp. 55-62

L. Batet, E. Mas de les Valls and L.A. Sedano. Mathematical models for tritium permeation analysis in liquid metal flows with hhelium bubbles (2014) Fusion Engineering and Design 89 (7-8), pp. 1158-1162

L. Batet, J.M. Alvarez-Fernandez, E. Mas de les Valls, V. Martinez-Quirorga, M. Perez, F. Reventos and L.A. Sedano. Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5-3D (2014) Fusion Engineeering and Design 89 (4), pp. 354-359

J. Aldama, L. Batet, S. Chiva, F. Martín-Fuertes, E. Mas de les Valls and R. Miró. Fluidodinámica Computacional y sus Aplicaciones en la Industria Nuclear. Nota técnica NT – 01/14 (2014) Sociedad Nuclear Española

L. Batet, E. Mas de les Valls, J. Fradera and F. Reventós. Desarrollo de modelos y herramientas de computación para análisis termo-fluidodinámicos en tecnología de fusión (2012) Nuclear España, enero 2012, pp. 10-15

Mas De Les Valls, E., Batet, L., De Medina, V., Fradera, J., Sanmartí, M., Sedano, L.A. Influence of thermal performance on design parameters of a He/LiPb dual coolant DEMO concept blanket design (2012) Fusion Engineering and Design, 87 (7-8), pp. 969-973.

Mas de les Valls, E., Batet, L., de Medina, V., Sedano, L.A. MHD thermofluid flow simulation of channels with a uniform thermal load as applied to HCLL breeding blankets for fusion technology (2012) Magnetohydrodynamics, 48 (1), pp. 157-168.

Veredas, G., Fradera, J., Fernández, I., Batet, L., Peñalva, I., Mesquida, L., Abell, J., Sempere, J., Martínez, I., Herrazti, B., Sedano, L. Design and qualification of an on-line permeator for the recovery of tritium from lead-lithium eutectic breeding alloy (2011) Fusion Engineering and Design, 86 (9-11), pp. 2365-2369.

Mas De Les Valls, E., Batet, L., De Medina, V., Fradera, J., Sedano, L.A. Qualification of MHD effects in dual-coolant DEMO blanket and approaches to their modelling (2011) Fusion Engineering and Design, 86 (9-11), pp. 2326-2329.

Batet, L., Fradera, J., Mas de les Valls, E., Sedano, L.A. Numeric implementation of a nucleation, growth and transport model for helium bubbles in lead-lithium HCLL breeding blanket channels: Theory and code development (2011) Fusion Engineering and Design, 86 (4-5), pp. 421-428.

Mas de les Valls, E., Batet, L., De Medina, V., Fradera, J., Sedano, L. Modelling of integrated effect of volumetric heating and magnetic field on tritium transport in a U-bend flow as applied to HCLL blanket concept (2011) Fusion Engineering and Design, 86 (4-5), pp. 341-356.

Fradera, J., Sedano, L., Mas De Les Valls, E., Batet, L. Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules (2011) Journal of Nuclear Materials, 417 (1-3), pp. 739-742.

Fradera, J., Batet, L., Mas De Les Valls, E., Sedano, L. Numeric implementation of two-phase tritium transport models for natural helium nucleated bubbles in lead-lithium. Implications for HCLL breeding blanket channels (2009) Proceedings - Symposium on Fusion Engineering, art. no. 5226440

Mas de les Valls, E., Sedano, L.A., Batet, L., Ricapito, I., Aiello, A., Gastaldi, O., Gabriel, F. Lead-lithium eutectic material database for nuclear fusion technology (2008) Journal of Nuclear Materials, 376 (3), pp. 353-357.