, ANSYS CFX Release 11, ANSYS CFX Reference Guide, issue.0, 2006.

D. Bestion, Two-phase CFD advances in the NURESIM and NURISP projects, Proceedings of the international conference on nuclear engineering ICONE 18, 2010.

M. J. Calleja, J. Jimenez, V. Sanchez, U. Imke, R. Stieglitz et al., Investigations of Boron Transport in a PWR Core with Coupled Neutronic/Thermal-hydraulic Codes Inside the NURESIM Platform, Annals of Nuclear Energy, vol.66, pp.74-84, 2014.

M. Calleja, R. Stieglitz, V. Sanchez, J. Jimenez, and U. Imke, A Coupled Neutronic/Thermalhydraulic Scheme between COBAYA3 and SUBCHANFLOW within the NURESIM Simulation Platform, 2012.

M. Däubler, N. Trost, and J. Jimenez, Recent developments in DYNSUB: new models, code optimization and parallelization, M&C, 2013.

S. Duerigen, U. Rohde, Y. Bilodid, and S. Mittag, The reactor dynamics code DYN3D and its trigonal-geometry nodal diffusion model, vol.78, pp.310-318, 2013.

A. Gomez, V. Sanchez, and S. Kliem, DYN3D/FLICA coupling Integration of DYN3D inside the NURESIM Platform. 17th Pacific Basin Nuclear Conference, 2010.

U. Grundmann and S. Kliem, Analyses of the OECD main steam line break benchmark with the DYN3D and ATHLET codes, Nuclear Technology, vol.142, pp.146-153, 2004.

J. Hadek, , 2011.

G. Hegyi, A. Kereszturi, and A. Tota, Qualification of the APOLLO2 Lattice Physics Code of the NURISP platform for VVER hexagonal lattices, Kerntechnik Journal issue, vol.04, pp.218-225, 2012.

J. J. Herrero, N. García-herranz, D. Cuervo, and C. Ahnert, Neighborhood-corrected interface discontinuity factors for multi-group pin-by-pin diffusion calculations for LWR, Annals of Nuclear Energy, vol.46, pp.106-115, 2012.

J. Jimenez, M. Calleja, and V. Sanchez, COBAYA3/FLICA4 coupling at the nodal level via SALOME, ROSA V Large Scale Test Facility (LSTF) System Description for the Third and Fourth Simulated Fuel Assemblies, 2003.

J. Jimenez, B. Chanaron, V. Sanchez, and X. Cheng, Advanced Numerical Simulation for Reactor Safety, 8th European Conference on EURATOM research and training in reactor systems, FISA 2013, program and abstracts, p.21, 2013.

G. Jimenez, J. J. Herrero, A. Gommlich, S. Kliem, D. Cuervo et al., Boron dilution transient simulation analyses in a PWR with neutronics/thermal hydraulics coupled codes in the NURISP project, Annals of Nuclear Energy, 2014.

S. Kliem, A. Gommlich, A. Grahn, U. Rohde, J. Schuetze et al., Development of Multi-Physics Code Systems based on the Reactor Dynamics Code DYN3D, vol.76, pp.160-165, 2011.

S. Kliem, S. Mittag, A. Gommlich, and P. Apanasevich, Definition of a PWR boron dilution benchmark, p.23, 2011.

S. Kliem, U. Rohde, and F. Weiss, Core response of a PWR to a slug of underborated water, Nucl. Eng. Design, vol.230, pp.121-132, 2004.

N. Kolev, VVER-1000 Coolant Transient Benchmark, Phase II (V1000CT-2), vol.2, 2006.

N. Kolev, I. Spasov, J. Lozano, N. Garcia-herranz, C. Ahnert et al., The analytic nodal diffusion solver ANDES in multigroups for 3D rectangular geometry: Development and performance analysis, Annals of Nuclear Energy, vol.35, issue.12, 2008.

J. A. Lozano, J. Jiménez, N. García-herranz, and J. M. Aragonés, Extension of the analytic nodal diffusion solver ANDES to triangular-Z geometry and coupling with COBRA-IIIc for hexagonal core analysis, Annals of Nuclear Energy, vol.37, pp.380-388, 2010.

R. Ochoa, J. Jimenez, and N. Garcia-herranz, Development of the neutronic/thermal-hydraulic coupling between COBAYA3 and SUBCHANFLOW. Application to Sodium Fast Reactors, 38th Annual meeting of the Spanish Nuclear Society, 2012.

A. Papukchiev, G. Lerchl, J. Weis, M. Scheuerer, and H. Austregesilo, Development of a Coupled 1D-3D Thermal-Hydraulic Code for Nuclear Power Plant Simulation and Its Application to a Pressurized Thermal Shock Scenario in PWR, Proc. of the NURETH-14 Conference, 2011.

N. Petrov, G. Todorova, N. Kolev, and F. Damian, Two-level MOC calculation scheme in APOLLO2 for cross-section libraries generation for LWR hexagonal assemblies, Proc. M&C, 2011.

N. Petrov, S. Sánchez-cervera, and J. J. Herrero, Steps ahead of the few-group cross-section library generation at the pin level, Proc. AER 2011 Conf. on VVER Reactor Physics and Safety, 2011.

I. Spasov, J. Jimenez, J. Lozano, and J. J. Herrero, COBAYA3/COBRA3 vs. CRONOS2/FLICA4 solutions of the V1000CT-EXT2 benchmark for VVER-1000, Proc. 19th AER Conf. on VVER Reactor Physics and Safety, 2009.

I. Spasov and N. Kolev, Full core FLICA4 input model for VVER MSLB analysis, NURESAFE D14, 2013.

I. Spasov, N. Kolev, N. Zheleva, G. Todorova, J. Jimenez et al., VVER MSLB benchmark solutions with CRONOS/FLICA and COBAYA/FLICA, NURISP D3.1.3.3a-Rev1 report, 2011.

. Rev2, , 2012.

I. Spasov, T. Tzanov, N. P. Kolev, and . Hádek, DYN3D/FLOCAL vs.COBAYA3/ FLICA4 solutions of the VVER-1000 MSLB benchmark, Proc. AER Conf. on VVER Reactor Physics and Safety, 2011.

G. Todorova, N. Petrov, N. Kolev, and F. Hugot, 2D core solutions for VVER-1000 with APOLLO2 and TRIPOLI4, Proc. AER 2009 Conf, 2009.

G. Todorova, N. Petrov, N. Zheleva, and . Kolev, Advanced calculation schemes and cross-section library generation in hexagonal geometry with APOLLO2, 21st Symposium of AER on VVER Reactor Physics and Reactor Safety, 2011.