Journal Papers

High-fidelity and high-resolution simulation of two different rod ejection accidents in a NuScale-like small modular reactor with conventional and accident tolerant fuels
Soti, Z.; Uffelen, P. V.; Schubert, A.; Valtavirta, V.; Tuominen, R.; Suikkanen, H.; Rintala, V.; Gommlich, A.; Fridman, E.; Bilodid, Y.; Mercatali, L.; Sanchez-Espinoza, V. H.
2025. Nuclear Engineering and Design, 441, 114183. doi:10.1016/j.nucengdes.2025.114183

Safety margins improvement by means of the passive heat removal system and the HA-2 in VVER-1000/V320 reactors
Redondo-Valero, E.; Queral, C.; Fernandez-Cosials, K.; Sanchez-Espinoza, V. H.
2025. Progress in Nuclear Energy, 187, 105825. doi:10.1016/j.pnucene.2025.105825

Source term dispersion analysis and construction of the probabilistic dispersion map around the Peach Bottom Unit-2 plant using the ASTEC and JRODOS codes
Murat, O.; Gabrielli, F.; Sanchez-Espinoza, V. H.
2025. Annals of Nuclear Energy, 215, 111277. doi:10.1016/j.anucene.2025.111277

An overcooling transient analysis in a CAREM-like SMR core using Serpent/Subchanflow
Huaccho Zavala, G.; Sánchez-Espinoza, V. H.; Mercatali, L.; Imke, U.
2025. Annals of Nuclear Energy, 214, 111204. doi:10.1016/j.anucene.2025.111204

Verification of the Coupled Code PARCS/TWOPORFLOW with Rod Ejection Accident Calculations for Small Modular Reactors
Campos-Muñoz, A.; Sanchez-Espinoza, V. H.; Redondo-Valero, E.; Queral, C.
2025. Nuclear Science and Engineering, 199 (sup1), 1–20. doi:10.1080/00295639.2024.2357953

HZP and HFP rod ejection analysis in a SMART-like reactor model using the GUARDYAN-SUBCHANFLOW coupled code system
Pázmán, E.; Tolnai, G.; Légrády, D.; Mercatali, L.; Huaccho, G.; Sanchez-Espinoza, V. H.
2025. Annals of Nuclear Energy, 211, 110988. doi:10.1016/j.anucene.2024.110988

Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package
Brumm, S.; Gabrielli, F.; Sanchez Espinoza, V.; Stakhanova, A.; Groudev, P.; Petrova, P.; Vryashkova, P.; Ou, P.; Zhang, W.; Malkhasyan, A.; Herranz, L. E.; Iglesias Ferrer, R.; Angelucci, M.; Berdaï, M.; Mascari, F.; Agnello, G.; Sevbo, O.; Iskra, A.; Martinez Quiroga, V.; Nudi, M.; Hoefer, A.; Pauli, E.-M.; Beck, S.; Tiborcz, L.; Coindreau, O.; Clark, G.; Lamont, I.; Zheng, X.; Kubo, K.; Lee, B.; Valincius, M.; Malicki, M.; Lind, T.; Vorobyov, Y.; Kotsuba, O.; Di Giuli, M.; Ivanov, I.; D’Onorio, M.; Giannetti, F.; Sevon, T.
2025. Annals of Nuclear Energy, 211, Art.-Nr.: 110962. doi:10.1016/j.anucene.2024.110962

Coupled serpent/subchanflow analysis with unstructured mesh interfaces for a hexagonal, plate-type VVR-KN fuel assembly
Huaccho Zavala, G.; Gheeraert, T.; Sánchez-Espinoza, V. H.; Almachi, J. C.; Imke, U.
2025. Frontiers in Nuclear Engineering, 4, Art.-Nr.: 1570855. doi:10.3389/fnuen.2025.1570855

Development of the 3D SP transport solver KANECS for nuclear reactor analysis
Duran-Gonzalez, J.; Campos-Muñoz, A.; Sanchez-Espinoza, V.-H.
2025. Frontiers in Energy Research, 13, 1498331. doi:10.3389/fenrg.2025.1498331

Major Achievements of the EC MUSA Project
Herranz, L. E.; Beck, S.; Sánchez-Espinoza, V. H.; Mascari, F.; Brumm, S.; Coindreau, O.; Paci, S.
2025. Nuclear Technology, 1–11. doi:10.1080/00295450.2024.2444081

Management of the SBLOCA sequences with HPIS failure in VVER-1000/V320 reactors; comparison with Westinghouse PWR strategies
Redondo-Valero, E.; Queral, C.; Fernandez-Cosials, K.; Sanchez-Espinoza, V. H.; Sánchez-Perea, M.; Groudev, P.
2024. Progress in Nuclear Energy, 177, Art.-Nr. 105414. doi:10.1016/j.pnucene.2024.105414

Assessing the impact of DIONISIO-SubChanFlow code coupling in nuclear fuel performance simulations
Cazado, M. E.; Sánchez-Espinoza, V. H.; Soba, A.
2024. Nuclear Engineering and Technology, 56 (11), 4843–4850. doi:10.1016/j.net.2024.06.048

Corrigendum to “Comparison of MSLB transient results using the 3D coupled code TRACEv5p05/PARCS and the system thermal hydraulic code RELAP5” [Ann. Nucl. Energy 203 (2024) 110518]
Stefanova, A.; Groudev, P.; Sanchez-Espinoza, V. H.; Zavala, G. H.
2024. Annals of Nuclear Energy, 205, Art.-Nr.: 110570. doi:10.1016/j.anucene.2024.110570

Comparison of MSLB transient results using the 3D coupled code TRACEv5p05/PARCS and the system thermal hydraulic code RELAP5
Stefanova, A.; Groudev, P.; Sanchez-Espinoza, V. H.; Zavala, G. H.
2024. Annals of Nuclear Energy, 203, 110518. doi:10.1016/j.anucene.2024.110518

Improved Analysis of the Short-Term Station Blackout Accidents of the Peach Bottom Unit-2 Reactor with ASTEC Including Radiological Impact and Statistical Analysis with JRODOS
Murat, O.; Sanchez-Espinoza, V.; Gabrielli, F.; Wang, S.; Stieglitz, R.; Queral, C.
2024. Nuclear Engineering and Design, 420, Art.-Nr.: 113012. doi:10.1016/j.nucengdes.2024.113012

Validation of the dynamic simulation capabilities of Serpent2/Subchanflow using experimental data from the research reactor SPERT IV D-12/25
Carlos Almachi, J.; Sánchez-Espinoza, V.; Imke, U.; Stieglitz, R.; Margulis, M.
2024. Nuclear Engineering and Design, 418, Art.-Nr.: 112840. doi:10.1016/j.nucengdes.2023.112840

CFD analysis of coolant mixing in VVER-1000/V320 reactor pressure vessel
Böttcher, M.; Bernard, O.; Mas, A.; Sanchez, V.; Nop, R.; Belaunde, F.; Bourcier, C.; Ruban, D.; Hashymov, A.; Halim, O.; Pucciarelli, A.; Forgione, N.
2024. Annals of Nuclear Energy, 197, Art.-Nr.: 110274. doi:10.1016/j.anucene.2023.110274

Assessment of ASTEC Thermal-Hydraulics against Plate Compact Steam Generator Experiments
Cazado, M. E.; Wang, S.; Gabrielli, F.; Laborde, L.; Zambaux, J.-A.; Ammirabile, L.; Murat, O.; Sánchez-Espinoza, V. H.
2024. Mecánica Computacional, 41 (18), 935–944. doi:10.70567/mc.v41i18.92

Analysis of Accident Scenarios in a Generic Natural Circulation Small Modular Reactor with the Astec Code in the Framework of the SASPAM-SA Project
Cazado, M. E.; Gabrielli, F.; Sánchez-Espinoza, V. H.
2024. Mecánica Computacional, 41 (18), 925–934. doi:10.70567/mc.v41i18.91

Development of NEMESI: A Multiparameter Library Generator Prototype for Industrial VVER and PWR Applications Based on APOLLO3®
Brighenti, A.; Vezzoni, B.; Hebert, A.; Calgaro, B.; Garcia-Cervantes, E. Y.; Huaccho Zavala, G.; Graziano, L.; Laurent, P.; Mercatali, L.; Mosca, P.; Previti, A.; Santandrea, S.; Vidal, J. F.; Willien, A.; Zmijarevic, I.
2024. Nuclear Science and Engineering, 1–18. doi:10.1080/00295639.2024.2340161

Multiscale analysis of the boron dilution sequence in the NuScale reactor using TRACE and SUBCHANFLOW
Sanchez-Torrijos, J.; Zhang, K.; Queral, C.; Imke, U.; Sanchez-Espinoza, V. H.
2023. Nuclear Engineering and Design, 415, Art.-Nr.: 112708. doi:10.1016/j.nucengdes.2023.112708

Safety margins improvement by means of the passive second stage hydroaccumulators in a VVER-1000/V320 reactor
Redondo-Valero, E.; Queral, C.; Fernandez-Cosials, K.; Sanchez-Espinoza, V.
2023. Nuclear Engineering and Design, 414, Art.-Nr.: 112644. doi:10.1016/j.nucengdes.2023.112644

KIT reactor safety research for LWRs: Research lines, numerical tools, and prospects
Sanchez-Espinoza, V. H.; Gabrielli, F.; Imke, U.; Zhang, K.; Mercatali, L.; Huaccho, G.; Duran, J.; Campos, A.; Stakhanova, A.; Murat, O.; Mercan, A. K.; Etcheto, J.; Steinbrück, M.; Stuckert, J.; Gabriel, S.; Ottenburger, S.; Stieglitz, R.; Tromm, W.
2023. Nuclear Engineering and Design, 414, Art.-Nr.: 112573. doi:10.1016/j.nucengdes.2023.112573

Uncertainty and sensitivity analysis of the ASTEC simulations results of a MBLOCA scenario in a generic KONVOI plant using the FSTC tool
Stakhanova, A.; Gabrielli, F.; Sanchez-Espinoza, V. H.; Hoefer, A.; Pauli, E. M.
2023. Annals of Nuclear Energy, 192, Art.-Nr.: 109964. doi:10.1016/j.anucene.2023.109964

Detail CFD simulation of the integrated reactor pressure vessel of SMART
Böttcher, M.; Sanchez-Espinoza, V.
2023. Progress in Nuclear Energy, 164, Art.-Nr.: 104854. doi:10.1016/j.pnucene.2023.104854

Uncertainty quantification for severe-accident reactor modelling: Set-up and first results of the Horizon-2020 project MUSA
Brumm, S.; Gabrielli, F.; Sanchez-Espinoza, V.; Stakhanova, A.; Nudi, M.; Groudev, P.; Ou, P.; Herranz, L. E.
2023. Annals of Nuclear Energy, 191, Art.-Nr.: 109919. doi:10.1016/j.anucene.2023.109919

Analysis of the short Term-Station Blackout accident at the Peach Bottom Unit-2 reactor with ASTEC including the estimation of the radiological impact with JRODOS
Murat, O.; Sanchez-Espinoza, V.; Gabrielli, F.; Stieglitz, R.; Queral, C.
2023. Nuclear Engineering and Design, 406, Art.-Nr.: 112227. doi:10.1016/j.nucengdes.2023.112227

Application of the MOCABA algorithm and the FSTC tool for source term predictions during severe accident scenarios
Stakhanova, A.; Gabrielli, F.; Sanchez-Espinoza, V. H.; Hoefer, A.; Pauli, E. M.
2023. Annals of Nuclear Energy, 184, Art.-Nr.: 109703. doi:10.1016/j.anucene.2023.109703

KIT Multi-scale thermal–hydraulic coupling methods for improved simulation of nuclear power plants
Hugo Sanchez-Espinoza, V.; Zhang, K.; Campos Muñoz, A.; Böttcher, M.
2023. Nuclear Engineering and Design, 405, Artkl.Nr.: 112218. doi:10.1016/j.nucengdes.2023.112218

Multiphysics modeling of a reactivity insertion transient at different fidelity levels in support to the safety assessment of a SMART-like small modular reactor
Mercatali, L.; Huaccho, G.; Sanchez-Espinoza, V.-H.
2023. Frontiers in Energy Research, 11, Art.-Nr.: 1130554. doi:10.3389/fenrg.2023.1130554

Validation of ASTEC2.1 using QUENCH-12 for VVER-Reactors
Mercan, A. K.; Sánchez-Espinoza, V. H.; Gabrielli, F.
2022. Nuclear Engineering and Design, 395, Art.-Nr.: 111840. doi:10.1016/j.nucengdes.2022.111840

Uncertainty and sensitivity analysis of the QUENCH-08 experiment using the FSTC tool
Stakhanova, A.; Gabrielli, F.; Sanchez-Espinoza, V. H.; Hoefer, A.; Pauli, E.
2022. Annals of nuclear energy, 169, Art.-Nr.: 108968. doi:10.1016/j.anucene.2022.108968

Verification of the Parallel Transport Codes Parafish and AZTRAN with the TAKEDA Benchmarks
Duran-Gonzalez, J.; Sanchez-Espinoza, V. H.; Mercatali, L.; Gomez-Torres, A.; Valle-Gallegos, E. del
2022. Energies, 15 (7), Art. Nr.: 2476. doi:10.3390/en15072476

Validation of the TWOPORFLOW code for the core analysis of liquid metal-cooled reactor with selected experiments
Feng, W.; Imke, U.; Zhang, K.; Sanchez-Espinoza, V.; Chen, H.
2022. Nuclear Engineering and Design, 390, Art.-Nr.: 111708. doi:10.1016/j.nucengdes.2022.111708

Implementation and validation of CHF-models in the two-phase porous-media code TWOPORFLOW
Jauregui Chavez, V.; Imke, U.; Sanchez-Espinoza, V. H.
2022. Nuclear engineering and design, 388, Article: 111631. doi:10.1016/j.nucengdes.2021.111631

Divertor of the European DEMO: Engineering and technologies for power exhaust
You, J. H.; Mazzone, G.; Visca, E.; Greuner, H.; Fursdon, M.; Addab, Y.; Bachmann, C.; Barrett, T.; Bonavolontà, U.; Böswirth, B.; Castrovinci, F. M.; Carelli, C.; Coccorese, D.; Coppola, R.; Crescenzi, F.; Di Gironimo, G.; Maio, P. A. Di; Di Mambro, G.; Domptail, F.; Dongiovanni, D.; Dose, G.; Flammini, D.; Forest, L.; Frosi, P.; Gallay, F.; Ghidersa, B. E.; Harrington, C.; Hunger, K.; Imbriani, V.; Li, M.; Lukenskas, A.; Maffucci, A.; Mantel, N.; Marzullo, D.; Minniti, T.; Müller, A. V.; Noce, S.; Porfiri, M. T.; Quartararo, A.; Richou, M.; Roccella, S.; Terentyev, D.; Tincani, A.; Vallone, E.; Ventre, S.; Villari, R.; Villone, F.; Vorpahl, C.; Zhang, K.
2022. Fusion engineering and design, 175, Art.-Nr.: 113010. doi:10.1016/j.fusengdes.2022.113010

Advanced numerical simulation and modeling for reactor safety – contributions from the CORTEX, McSAFER, and METIS projects
Demazière, C.; Sanchez-Espinoza, V. H.; Zentner, I.
2022. EPJ Nuclear Sciences & Technologies, 8, Art.-Nr.: 29. doi:10.1051/epjn/2022026

Analysis of MBLOCA and LBLOCA success criteria in VVER-1000/V320 reactors. New proposals for PSA Level 1
Redondo-Valero, E.; Queral, C.; Fernandez-Cosials, K.; Sanchez-Espinoza, V. H.
2022. Nuclear Engineering and Technology, 55 (2), 623–639. doi:10.1016/j.net.2022.10.006

High-Fidelity Steady-State and Transient Simulations of an MTR Research Reactor Using Serpent2/Subchanflow
Almachi, J. C.; Sánchez-Espinoza, V. H.; Imke, U.
2022. Energies, 15 (4), Art.-Nr.: 1554. doi:10.3390/en15041554

An Advanced TRACE Modeling Approach: Automatic Connection of 3D Cartesian and Cylindrical VESSEL Components in Integral Plant Models
Zhang, K.; Sanchez-Espinoza, V. H.
2022. Energies, 15 (12), Art.-Nr. 4384. doi:10.3390/en15124384

Sistemas de seguridad de los reactores VVER Gen-III/Gen-III+
Salazar, C. Q.; Sánchez-Espinoza, V. H.; Egelkraut, D.; Cosials, K. F.; Redondo Valero, E.
2021. Nuclear España, (Octubre)

Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor
García, M.; Vočka, R.; Tuominen, R.; Gommlich, A.; Leppänen, J.; Valtavirta, V.; Imke, U.; Ferraro, D.; Van Uffelen, P.; Milisdörfer, L.; Sanchez-Espinoza, V.
2021. Nuclear Engineering and Technology, 53 (10), 3133–3150. doi:10.1016/j.net.2021.04.023

Development and verification of the coupled thermal–hydraulic code – TRACE/SCF based on the ICoCo interface and the SALOME platform
Zhang, K.; Muñoz, A. C.; Sanchez-Espinoza, V. H.
2021. Annals of nuclear energy, 155, Art. Nr.: 108169. doi:10.1016/j.anucene.2021.108169

The H2020 McSAFER Project: Main Goals, Technical Work Program, and Status
Sanchez-Espinoza, V. H.; Gabriel, S.; Suikkanen, H.; Telkkä, J.; Valtavirta, V.; Bencik, M.; Kliem, S.; Queral, C.; Farda, A.; Abéguilé, F.; Smith, P.; Uffelen, P. V.; Ammirabile, L.; Seidl, M.; Schneidesch, C.; Grishchenko, D.; Lestani, H.
2021. Energies, 14 (19), Article: 6348. doi:10.3390/en14196348

The EC MUSA project on management and uncertainty of severe accidents: Main pillars and status
Herranz, L. E.; Beck, S.; Sánchez-Espinoza, V. H.; Mascari, F.; Brumm, S.; Coindreau, O.; Paci, S.
2021. Energies, 14 (15), 4473. doi:10.3390/en14154473

Simulation of low-enriched uranium burnup in Russian VVER-1000 reactors with the Serpent Monte-Carlo code
Mercatali, L.; Beydogan, N.; Sanchez-Espinoza, V. H.
2021. Nuclear Engineering and Technology, 53 (9), 2830–2838. doi:10.1016/j.net.2021.03.014

Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from a Pre-Konvoi PWR reactor
García, M.; Bilodid, Y.; Basualdo Perello, J.; Tuominen, R.; Gommlich, A.; Leppänen, J.; Valtavirta, V.; Imke, U.; Ferraro, D.; Van Uffelen, P.; Seidl, M.; Sanchez-Espinoza, V.
2021. Nuclear Engineering and Design, 379, Art.-Nr.: 111173. doi:10.1016/j.nucengdes.2021.111173

Extension and validation of the SubChanFlow code for the thermo-hydraulic analysis of MTR cores with plate-type fuel assemblies
Almachi, J. C.; Sánchez-Espinoza, V.; Imke, U.
2021. Nuclear Engineering and Design, 379, Art.-Nr.: 111221. doi:10.1016/j.nucengdes.2021.111221

A Collision-based Domain Decomposition scheme for large-scale depletion with the Serpent 2 Monte Carlo code
García, M.; Leppänen, J.; Sanchez-Espinoza, V.
2021. Annals of nuclear energy, 152, Art.-Nr.: 108026. doi:10.1016/j.anucene.2020.108026

Preliminary validation of ASTEC V2.2.b with the QUENCH-20 BWR bundle experiment
Murat, O.; Sanchez-Espinoza, V.; Wang, S.; Stuckert, J.
2020. Nuclear engineering and design, 370, 110931. doi:10.1016/j.nucengdes.2020.110931

OECD/NRC PWR MOX/UO2 core transient benchmark pin-by-pin solutions using Serpent/SUBCHANFLOW
Ferraro, D.; Valtavirta, V.; García, M.; Imke, U.; Tuominen, R.; Leppänen, J.; Sanchez-Espinoza, V.
2020. Annals of nuclear energy, 147, Art.-Nr. 107745. doi:10.1016/j.anucene.2020.107745

Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for the SPERT-IIIE hot full power tests
Ferraro, D.; García, M.; Valtavirta, V.; Imke, U.; Tuominen, R.; Leppänen, J.; Sanchez-Espinoza, V.
2020. Annals of nuclear energy, 142, Article No. 107387. doi:10.1016/j.anucene.2020.107387

Multi-scale coupling of CFD code and sub-channel code based on a generic coupling architecture
Zhang, X.; Zhang, K.; Sanchez-Espinoza, V. H.; Chen, H.
2020. Annals of nuclear energy, 141, Article: 107353. doi:10.1016/j.anucene.2020.107353

The multiscale thermal‐hydraulic simulation for nuclear reactors: A classification of the coupling approaches and a review of the coupled codes
Zhang, K.
2020. International journal of energy research, 44 (5), 3295–3315. doi:10.1002/er.5111

Statistical characterization of NPP transients: Application to PWR LBLOCA
Fernández-Cosials, K.; Queral, C.; Zugazagoitia, E.; Magán, J.; Sanchez-Torrijos, J.; Sánchez-Espinoza, V. H.; Posada, J. M.
2020. Annals of nuclear energy, 144, Article: 107505. doi:10.1016/j.anucene.2020.107505

Development of the coupled code – TRACE/TrioCFD based on ICoCo for simulation of nuclear power systems and its validation against the VVER-1000 coolant-mixing benchmark
Zhang, K.; Zhang, X.; Sanchez-Espinoza, V.; Stieglitz, R.
2020. Nuclear engineering and design, 362, Art.Nr.: 110602. doi:10.1016/j.nucengdes.2020.110602

Serpent2-SUBCHANFLOW pin-by-pin modelling capabilities for VVER geometries
García, M.; Ferraro, D.; Valtavirta, V.; Tuominen, R.; Imke, U.; Leppänen, J.; Sanchez-Espinoza, V.
2020. Annals of nuclear energy, 135, Article: 106955. doi:10.1016/j.anucene.2019.106955

Advanced numerical simulation and modelling for reactor safety - contributions from the CORTEX, HPMC, MCSAFE and NURESAFE Projects
Demazière, C.; Sanchez-Espinoza, V. H.; Chanaron, B.
2020. EPJ Nuclear Sciences & Technologies, 6, Article: 42. doi:10.1051/epjn/2019006

The Dynamic-Implicit-Additional-Source (DIAS) method for multi-scale coupling of thermal-hydraulic codes to enhance the prediction of mass and heat transfer in the nuclear reactor pressure VESSEL
Zhang, K.; Sanchez-Espinoza, V. H.
2020. International journal of heat and mass transfer, 147, Article No.118987. doi:10.1016/j.ijheatmasstransfer.2019.118987

A Serpent2-SUBCHANFLOW-TRANSURANUS coupling for pin-by-pin depletion calculations in Light Water Reactors
García, M.; Tuominen, R.; Gommlich, A.; Ferraro, D.; Valtavirta, V.; Imke, U.; Van Uffelen, P.; Mercatali, L.; Sanchez-Espinoza, V.; Leppänen, J.; Kliem, S.
2020. Annals of nuclear energy, 139, Article No.107213. doi:10.1016/j.anucene.2019.107213

Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for a PWR minicore
Ferraro, D.; García, M.; Valtavirta, V.; Imke, U.; Tuominen, R.; Leppänen, J.; Sanchez-Espinoza, V.
2020. Annals of nuclear energy, 137, Article No.107090. doi:10.1016/j.anucene.2019.107090

Integration of the subchannel thermal-hydraulic code SubChanFlow into the reactor dynamics code PARCS: Development and testing based on a computational benchmark
Basualdo, J. R.; Sánchez-Espinoza, V.; Stieglitz, R.; Macián-Juan, R.
2020. Progress in nuclear energy, 119, Art. Nr.: 103138. doi:10.1016/j.pnucene.2019.103138

Coupling of TRACE and SubChanFlow based on the Exterior Communication Interface
Zhang, K. L.; Sanchez-Espinoza, V. H.
2020. Progress in nuclear energy, 119, Art. Nr.: 103040. doi:10.1016/j.pnucene.2019.103040

Optimization and verification of the coupled code TRACE/SubChanFlow using the VVER-1000 coolant mixing benchmark data
Zhang, K.; Sanchez-Espinoza, V. H.
2019. Nuclear engineering and design, 353, Article No.110238. doi:10.1016/j.nucengdes.2019.110238

Parcs-Subchanflow-Transuranus Multiphysics coupling for high fidelity PWR reactor core simulations: Preliminary Results
Basualdo, J. R.; Sánchez-Espinoza, V. H.; Stieglitz, R.; Rafael, M.-J.
2019. Atw, 64 (5), 275–279

Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark
Skorek, T.; Crécy, A. de; Kovtonyuk, A.; Petruzzi, A.; Mendizábal, R.; Alfonso, E. de; Reventós, F.; Freixa, J.; Sarrette, C.; Kyncl, M.; Pernica, R.; Baccou, J.; Fouet, F.; Probst, P.; Chung, B.-D.; Tram, T. T.; Oh, D.-Y.; Gusev, A.; Falkov, A.; Shvestov, Y.; Li, D.; Liu, X.; Zhang, J.; Alku, T.; Kurki, J.; Jäger, W.; Sánchez, V.; Wicaksono, D.; Zerkak, O.; Pautz, A.
2019. Nuclear engineering and design, 354, Article No.110199. doi:10.1016/j.nucengdes.2019.110199

Analysis of a control rod ejection accident in a boron-free small modular reactor with coupled neutronics/thermal-hydraulics code
Alzaben, Y.; Sanchez-Espinoza, V. H.; Stieglitz, R.
2019. Annals of nuclear energy, 134, 114–124. doi:10.1016/j.anucene.2019.06.009

Analysis of a steam line break accident of a generic SMART-plant with a boron-free core using the coupled code TRACE/PARCS
Alzaben, Y.; Sanchez-Espinoza, V. H.; Stieglitz, R.
2019. Nuclear engineering and design, 350, 33–42. doi:10.1016/j.nucengdes.2019.05.002

Core neutronics and safety characteristics of a boron-free core for Small Modular Reactors
Alzaben, Y.; Sanchez-Espinoza, V. H.; Stieglitz, R.
2019. Annals of nuclear energy, 132, 70–81. doi:10.1016/j.anucene.2019.04.017

Serpent/SCF pin-level multiphysics solutions for the VERA Fuel Assembly benchmark
Ferraro, D.; Garcia, M.; Imke, U.; Valtavirta, V.; Leppänen, J.; Sanchez-Espinoza, V.
2019. Annals of nuclear energy, 128, 102–114. doi:10.1016/j.anucene.2018.12.047

Further development of a thermal hydraulics two-phase flow tool
Chavez, V. J.; Imke, U.; Jimenez, J.; Sanchez-Espinoza, V. H.
2018. Atw, 63 (6/7), 401–404

CESAM – Code for European severe accident management, EURATOM project on ASTEC improvement
Nowack, H.; Chatelard, P.; Chailan, L.; Hermsmeyer, S.; Sanchez, V.; Herranz, L.
2018. Annals of nuclear energy, 116, 128–136. doi:10.1016/j.anucene.2018.02.021

Assessment of primary and secondary bleed and feed procedures during a Station Blackout in a German Konvoi PWR using ASTECV2.0
Gómez-García-Toraño, I.; Sánchez-Espinoza, V.-H.; Stieglitz, R.; Queral, C.; Rebollo, M.-J.
2018. Annals of nuclear energy, 113, 476–492. doi:10.1016/j.anucene.2017.11.053

Development and validation of the new coupled code system TRADYN
González-Vargas, J. Á.; Sánchez Espinoza, V. H.; Stieglitz, R.; Macian-Juan, R.
2018. Annals of nuclear energy, 112, 685–692. doi:10.1016/j.anucene.2017.07.027

TWOPORFLOW: A two-phase flow porous media code, main features and validation with BWR-relevant bundle experiments
Jauregui Chavez, V.; Imke, U.; Sanchez-Espinoza, V.
2018. Nuclear engineering and design, 338, 181–188. doi:10.1016/j.nucengdes.2018.08.009

Analysis of PWR SBO sequences with RCP passive thermal shutdown seals
Mena-Rosell, L.; Queral, C.; Ruiz-Zapatero, M.; Sanchez-Perea, M.; Jimenez, G.; Gomez-Magan, J.; Hortal, J.; Sanchez-Espinoza, V.-H.
2018. Journal of nuclear science and technology, 55 (6), 649–662. doi:10.1080/00223131.2018.1428125

Analysis of primary bleed and feed strategies for selected SBLOCA sequences in a German Konvoi PWR using ASTEC V2.0
Gómez-García-Toraño, I.; Sánchez-Espinoza, V.-H.; Stieglitz, R.; Queral, C.
2017. Annals of nuclear energy, 110, 818–832. doi:10.1016/j.anucene.2017.08.003

Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes
Spasov, I.; Mitkov, S.; Kolev, N. P.; Sanchez-Cervera, S.; Garcia-Herranz, N.; Sabater, A.; Cuervo, D.; Jimenez, J.; Sanchez, V. H.; Vyskocil, L.
2017. Nuclear engineering and design, 321, 26–37. doi:10.1016/j.nucengdes.2017.03.032

Investigation of SAM measures during selected MBLOCA sequences along with Station Blackout in a generic Konvoi PWR using ASTECV2.0
Gómez-García-Toraño, I.; Sánchez Espinoza, V. H.; Stieglitz, R.
2017. Annals of nuclear energy, 105, 226–239. doi:10.1016/j.anucene.2017.02.030

Validation of ASTECV2.1 based on the QUENCH-08 experiment
Gómez-García-Toraño, I.; Sánchez-Espinoza, V.-H.; Stieglitz, R.; Stuckert, J.; Laborde, L.; Belon, S.
2017. Nuclear engineering and design, 314, 29–43. doi:10.1016/j.nucengdes.2016.12.039

Application of the ATHLET/COBRA-TF thermal-hydraulics coupled code to the analysis of BWR ATWS
Jimenez Escalante, J.; Di Marcello, V.; Sanchez Espinoza, V.; Perin, Y.
2017. Nuclear engineering and design, 321, 318–327. doi:10.1016/j.nucengdes.2016.10.001

The European ITER Test Blanket Modules : EUROFER97 material and TBM’s fabrication technologies development and qualification
Zmitko, M.; Carin, Y.; Thomas, N.; Simon-Perret, M.; LiPuma, A.; Forest, L.; Tosi, J.; Aiello, G.; Cogneau, L.; Rey, J.; Neuberger, H.; Aktaa, J.; Gaganidze, E.; Zhang, K.; Pierredon, N.; Lejeail, Y.; Lamagnere, P.; Poitevin, Y.
2016. Fusion engineering and design, 124, 767–773. doi:10.1016/j.fusengdes.2017.04.051

Fuel depletion analysis of a small sodium fast reactor with KANEXT and SERPENT
Lopez-Solis, R. C.; Francois, J. L.; Bastida-Ortiz, G. E.; Becker, M.; Sanchez-Espinoza, V. H.
2016. Annals of nuclear energy, 98, 26–35. doi:10.1016/j.anucene.2016.07.024

Validation and application of the system code ATHLET-CD for BWR severe accident analyses
Di Marcello, V.; Imke, U.; Sanchez, V.
2016. Nuclear engineering and design, 307, 284–298. doi:10.1016/j.nucengdes.2016.07.013

Validation of the Serpent 2-DYNSUB code sequence using the Special Power Excursion Reactor Test III (SPERT III)
Knebel, M.; Mercatali, L.; Sanchez, V.; Stieglitz, R.; Macian-Juan, R.
2016. Annals of Nuclear Energy, 91, 79–91. doi:10.1016/j.anucene.2016.01.005

Accelerating COBAYA3 on multi-core CPU and GPU systems using PARALUTION
Trost, N.; Jimenez, J.; Lukarski, D.; Sanchez, V.
2015. Annals of nuclear energy, 82, 252–259. doi:10.1016/j.anucene.2014.08.005

Large-scale Monte Carlo neutron transport calculations with thermal hydraulic feedback
Ivanov, A.; Sanchez, V.; Stieglitz, R.; Ivanov, K.
2015. Annals of Nuclear Energy, 84, 204–219. doi:10.1016/j.anucene.2014.12.030

Validation of the thermal-hydraulic system code ATHLET based on selected pressure drop and void fraction BFBT tests
Di Marcello, V.; Jimenez Escalante, J.; Sanchez Espinoza, V.
2015. Nuclear engineering and design, 288, 183–194. doi:10.1016/j.nucengdes.2015.04.003

SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark
Mercatali, L.; Venturini, A.; Daeubler, M.; Sanchez, V. H.
2015. Annals of nuclear energy, 83, 328–341. doi:10.1016/j.anucene.2015.03.036

Advanced multi-physics simulation for reactor safety in the framework of the NURESAFE project
Chanaron, B.; Ahnert, C.; Crouzet, N.; Sanchez, V.; Kolev, N.; Marchand, O.; Kliem, S.; Papukchiev, A.
2015. Annals of nuclear energy, 84, 166–177. doi:10.1016/j.anucene.2014.12.013

Static and transient pin-by-pin simulations of a full PWR core with extended coupled code system DYNSUB
Daeubler, M.; Trost, N.; Jimenez, J.; Sanchez, V.; Stieglitz, R.; Macian-Juan, R.
2015. Annals of nuclear energy, 84, 31–44. doi:10.1016/j.anucene.2014.09.057

High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW
Daeubler, M.; Ivanov, A.; Sjenitzer, B. L.; Sanchez, V.; Stieglitz, R.; Macian-Juan, R.
2015. Annals of nuclear energy, 83, 352–375. doi:10.1016/j.anucene.2015.03.040