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Janin, D., Seidl, M., Soldevila, M., Douce, S., Arnaud, G., Damian, F., Poinot, C., Macian, R.HCSMR fuel assembly optimization with APOLLO2 and Uranie codesProceedings PHYSOR 20162016
Holt, L., Rohde, U., Kliem, S., Baier, S., Seidl, M., Van Uffelen, P., Macián-Juan, R.Investigation of feedback on neutron kinetics and thermal hydraulics from detailed online fuel behavior modeling during a boron dilution transient in a PWR with the two-way coupled code system DYN3D-TRANSURANUSNuclear Engineering and Design2016297
Knebel, M., Mercatali, L., Sanchez, V., Stieglitz, R., Macian-Juan, R.Validation of the Serpent 2-DYNSUB code sequence using the Special Power Excursion Reactor Test III (SPERT III)Annals of Nuclear Energy2016
Frankl, M., Macián-Juan, R.Photonuclear benchmarks of C, Al, Cu, Ta, Pb, and U from the ENDF/B-VII cross-section library ENDF7U using MCNPXNuclear Science and Engineering2016
Al Issa, S., Macian-Juan, R.Experimental investigation and CFD validation of countercurrent flow limitation (CCFL) in a large-diameter PWR hot-leg geometryJournal of Nuclear Science and Technology2016
Cappia, F., Pizzocri, D.ac, Marchetti, M., Schubert, A., Van Uffelen, P., Luzzi, L., Papaioannou, D., Macián-Juan, R., Rondinella, V.VMicrohardness and Young's modulus of high burn-up UO2 fuelJournal of Nuclear Materials2016479
Cappia, F., Pizzocri, D., Schubert, A., Van Uffelen, P., Paperini, G., Pellottiero, D., Macián-Juan, R., Rondinella, V.V.Critical assessment of the pore size distribution in the rim region of high burnup UO2 fuelsJournal of Nuclear Materials2016480
Périn, YannDevelopment of a Multi-Physics, Multi-Scale simulation tool for LWR safety analysis2016Dissertation163 p.
He, XunValidation of the TRACE Code for the System Dynamic Simulations of the Molten Salt Reactor Experiment and the Preliminary Study on the Dual Fluid Molten Salt Reactor2016Dissertation179 p.