Boldt, Felix.Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD.ASME J of Nuclear Rad Sci. .2019.5(2)

Du, Z., Sheng, D.-Y., Seidl, M., Macián-Juan, R..Investigations of neutron noise induced by transient cross flow in a PWR reactor core. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics.2019

Al Issa, S., Macian-Juan, R..A correlation of the water film thickness and friction factor for supercritical /subcritical transition in a hot-leg pipe geomtery. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics.NURETH 2019.2019

Wang, X., Zhang, Q., He, X., Du, Z., Seidl, M., Macian-Juan, R., Czerski, K., Dabrowski, M..Neutron physical feasibility of small modular design of dual fluid reactor. International Conference on Nuclear Engineering,. ICONE, 2019-May.2019

Du, Z., Seidl, M., Macian-Juan, R..Implementation of piN power factors in the ANSYS CFX/PARCS coulpling system for local analysis of neutron oscillation. International Conference on Nuclear Engineering,. ICONE, 2019-May.2019

Basualdo, J.R., Sánchez-Espinoza, V., Stieglitz, R., Macián-Juan, R..Integration of the subchannel thermal-hydraulic code SubChanFlow into the reactor dynamics code PARCS: Development and testing based on a computational benchmark. Progress in Nuclear Energy.2019

Wang, X., Liu, C., Macian-Juan, R..Preliminary hydraulic analysis of the distribution zone in the Dual Fluid Reactor concept.Progress in Nuclear Energy.2019. 110

He, X., Zeng, C., Yu, X., Du, Z., Macián-Juan, R..Feasibility Study on Conceptual Design of Dual Fluid Fast Reactor. Hedongli Gongcheng/Nuclear Power Engineering.2019. 40 (1)

Al Issa, S., Murase, M., Tomiyama, A., Hayashi, K., Macián-Juan, R..On CCFL at a PWR Hot-Leg Pipe Geometry and Comparison Between Results in COLLIDER 1/4th- and Kobe 1/15th-Scaled Facilities. Nuclear Science and Engineering.2019. 193 (1-2)

Wang, X., Zhang, Q., Zhuang, K., He, X., Seidl, M., Macian-Juan, R..Neutron physics of the liquid-fuel heat-pipe reactor concept with molten salt fuel—Static calculations.International Journal of Energy Research.2019. 43 (14)