Publications

Selected publications related to the KAMPS platform and our research

Journal Papers

2025

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

2024

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

2023

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

2022

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

2021

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

2020

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

2019

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

2018

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

2017

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

2016

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

2015

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

Conference Papers

2025

Validation of SERPENT2/SUBCHANFLOW using Beginning-of-Transient Experimental Data from Rostov-2 VVER-1000 Core at 36.37 EFPD
Beydogan, N.; Sanchez-Espinoza, V. H.
2025. 7th Rostov-2 VVER-1000 Multi-Physics Transient Benchmark Workshop (2025), Cambridge, United Kingdom, July 4, 2025

2024

Analysis of the impact of passive safety systems on accidental sequences of VVER-1000 reactors
Redondo-Valero, E.; Queral, C.; Fernandez-Cosials, K.; Sanchez-Espinoza, V. H.
2024. 7th International Conference on Nuclear and Renewable Energy Resources (NURER 2024) : Conference Proceedings. Ed.: H.M. Sahin, 5 – 18, Curran Associates, Inc

KIT Investigations of the VVER-1000 plant behavior under design basis accidents
Sanchez-Espinoza, V. H.; Beydogan, N.; Huaccho-Zavala, G.
2024. th International Conference on Nuclear and Renewable Energy Resources (NURER 2024) : Conference Proceedings. Ed.: H.M. Sahin, 86 – 99, Curran Associates, Inc

Comparative analysis of accidental sequences with conventional and Advanced Tolerant Fuels (ATF) in VVER-1000 reactors
Redondo-Valero, E.; Queral, C.; Sanchez-Torrijos, J.; Castro-Gonzalez, E.; Sanchez-Espinoza, V. H.
2024. 7th International Conference on Nuclear and Renewable Energy Resources (NURER 2024) : Conference Proceedings. Ed.: H.M. Sahin, 19 – 28, Curran Associates, Inc

Overcooling transient analysis in a CAREM-like SMR design using different simulation approaches
Huaccho, G.; Lestani, H.; Sanchez-Espinoza, V. H.
2024. Workshop on Core and Plant Simulation with an Emphasis on Fuel Behaviour in Light Water Reactor Based Small Modular Reactors (2024), Vienna, Austria, February 27–29, 2024

SMART analysis with multi-scale multi-physics coupled codes involving TRACE SCF and PARCS
Zhang, K.
2024. IAEA Workshop (2024), Vienna, Austria, February 27–29, 2024

The H2020 McSAFER: High-Performance Advanced Methods and Experimental Investigations for the Safety Evaluation of Generic Small Modular Reactors
Sanchez-Espinoza, V. H.
2024. Workshop on Core and Plant Simulation with an Emphasis on Fuel Behaviour in Light Water Reactor Based Small Modular Reactors (2024), Vienna, Austria, February 27–29, 2024

SMART Rod Ejection Accident (REA) Analysis using Different Simulation Approaches
Zhang, K.
2024. IAEA Workshop (2024), Vienna, Austria, February 27–29, 2024

SMART SLB analysis with OpenFOAM/TRACE/ PARCS
Zhang, K.
2024. IAEA Workshop (2024), Vienna, Austria, February 27–29, 2024

2023

Study of SMART Steam Line Break with the coupled codes TRACE-PARCS and TRACE-PANTHER
Etcheto, J.; Sanchez, V. H.; Palmans, N.
2023. Proceedings of M&C 2023

Modeling of an Overcooling Transient Scenario in a CAREM-like Small Modular Reactor
Mercatali, L.; Sanchez-Espinoza, V. H.; Lestani, H.; Dalinger, M.
2023. Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH), 5882–5894, American Nuclear Society (ANS)

A Super-Homogenisation (SPH)-based Pin-wise Cross-Section (XS) Optimization Scheme for PARCS: Development Verification and First Application to a Small Modular Reactor (SMR)
Zhang, K. L.; Mercatali, L.; Sanchez-Espinoza, V. H.
2023. Proceedings of M&C 2023 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Canadian Nuclear Society (CNS)

The H2020 McSAFER Project: Experimental and Analytical Investigations for the Safety Evaluation of Water-Cooled SMRs
Sanchez-Espinoza, V. H.
2023. Proceedings of M&C 2023 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Canadian Nuclear Society (CNS)

Development of a multi-parameter library generator prototype for VVER and PWR applications based on APOLLO3
Brighenti, A.; Vezzoni, B.; Hébert, A.; Calgaro, B.; Garcia-Cervantes, E.; Huaccho Zavala, G.; Graziano, L.; Laurent, P.; Mercatali, L.; Mosca, P.; Previti, A.; Santandrea, S.; Vidal, J.-F.; Willien, A.; Zmijarevic, I.
2023. Proceedings of M&C 2023 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Canadian Nuclear Society (CNS)

Analysis of C5G7-TD benchmark with the AZTRAN code
Duran-Gonzalez, J.; Sanchez-Espinoza, V.; Gomez-Torres, A.; Valle-Gallegos, E. del
2023. Proceedings of M&C 2023 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Canadian Nuclear Society (CNS)

Study of Anticipated Transient Without Scram with the Coupled code TRACE SubChanFlow for the SMART Small Modular Reactor
Etcheto, J.; Sanchez Espinoza, V. H.; Zhang, K. L.
2023. Proceedings of M&C 2023 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Canadian Nuclear Society (CNS)

Multi-scale Coupling of TRACE and SubChanFlow (SCF) in the SALOME Platform using the Domain Decomposition (DD) Method and a Conservative Data Transfer Approach
Zhang, K.; Sanchez-Espinoza, V.-H.
2023. 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 1066–1075, American Nuclear Society (ANS)

Validation of Neutronic and Thermal-Hydraulic Multi-physics Calculations for SMRs Rod Ejection Accident with PARCS/TWOPORFLOW
Campos-Munoz, A.; Sanchez Espinoza, V.; Redondo-Valero, E.
2023. Proceedings of M&C 2023 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Canadian Nuclear Society (CNS)

Thermal-Hydraulic Analysis of Sbloca Sequences with HPIS Failure and Secondary Side Depressurization in VVER-1000/V-320 Reactors
Redondo-Valero, E.; Sanchez-Espinoza, V. H.; Queral, C.; Gomez-Magan, J.; Fernandez-Cosials, K.
2023. 30th International Conference on Nuclear Engineering (ICONE 30), Kyoto, Japan, 21-26 May 2023, The American Society of Mechanical Engineers (ASME)

Validation of Neutronic and Thermal-Hydraulic Multi-physics Calculations for SMRs Rod Ejection Accident with PARCS/TWOPORFLOW
Campos-Munoz, A.; Sanchez Espinoza, V.; Redondo-Valero, E.
2023. The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), Niagara Falls, Canada, August 13–17, 2023

The H2020 McSAF0E1R: High-Performance Advanced Methods and Experimental Investigations for the Safety Evaluation of Generic Small Modular Reactors
Sanchez-Espinoza, V. H.; Valtavirta, V.; Bencik, M.; Kliem, S.; Queral, C.; Chochet, S.; Smith, P.; Uffelen, P. van; Seidl, M.; Schneidesch, C.; Grishchenko, D.; Lestani, H.
2023. Workshop on the Safety of Small Modular, Advanced and Fusion Reactors (2023), Celje, Slovenia, June 20–21, 2023

Overview and Outlook of the Computational Activities at KIT for the Safety Assessment and the Radiological Risk Prediction of Nuclear Power Plants
Gabrielli, F.; Sanchez-Espinoza, V. H.
2023. Jahrestagung des KIT-Zentrums Energie (2023), Karlsruhe, Germany, June 27, 2023

Multi scale Simulation of NuScale like SMR with PARCS/TWOPORFLOW/TRACE
Campos Muñoz, A.; Sanchez Espinoza, V.
2023. CAMP-Spring Meeting (2023), Budapest, Hungary, May 23–25, 2023

KIT Advanced Multiphysics Schemes for LWRs Applications
Mercatali, L.; Huaccho, G.; Sanchez-Espinoza, V. H.
2023. AAA Workshop (2023), Garching bei München, Germany, May 10, 2023

KIT Safety Research Activities for LWR, LW SMR and Research Reactors
Sánchez-Espinoza, V. H.; Zhang, K.; Mercatali, L.; Huaccho, G.; Almachi, J. C.; Imke, U.; Gabrielli, F.
2023. SNETP FORUM (2023), Gothenburg, Sweden, May 15–17, 2023

KIT Computational Route for the Safety Assessment and Radiological Risk Prediction of NPPs
Sánchez-Espinoza, V. H.; Gabrielli, F.; Zhang, K.; Mercatali, L.; Imke, U.; Steinbrück, M.; Stuckert, J.; Gabriel, S.; Ottenburger, S.; Stieglitz, R.; Tromm, W.
2023. RSK-AST Meeting (2023), Online, May 11, 2023

Preliminary validation of Serpent2/Subchanflow using the Spert IV D-12/25 Data
Almachi, J. C.; Sanchez-Espinoza, V. H.
2023. Eurpean Research Reactor Conference 2023: Proceedings

2022

Extension of the Validation Basis of Subchanflow by Using Measured Data From the IEA-R1 Research Reactor
Almachi, J. C.; Sanchez-Espinoza, V. H.
2022. XXXIII Congreso Anual de la Sociedad Nuclear Mexicana Energ´ıa Nuclear: La fuente de energ´ıa m´as EFICIENTE para mitigar el calentamiento global. Memorias en formato digital

Verification of Neutronic and Thermal-hydraulic Multi-physics Steady-State Calculations for Small Modular Reactors with PARCS and TWOPORFLOW
Campos Muñoz, A.; Sanchez-Espinoza, V. H.
2022. XXXIII Congreso Anual de la Sociedad Nuclear Mexicana Energía Nuclear: la fuente de energía más EFICIENTE para mitigar el calentamiento global (2022), Veracruz, Mexico, November 13–16, 2022

Status of the H2020 MCSafer Project-experimental and analytical investigations for the safety evaluation of water-cooled SMRS
Sanchez-Espinoza, V. H.; Gabriel, S.; Suikkanen, H.; Valtavirta, V.; Bencik, M.; Kliem, S.; Queral, C.; Farda, A.; Smith, P.; Uffelen, P. van; Seidl, M.; Schneidesch, C.; Grishchenko, D.; Lestani, H.
2022. International Conference on Topical Issues in Nuclear Installation Safety: Strengthening Safety of Evolutionary and Innovative Reactor Designs (2022), Vienna, Austria, October 18–21, 2022

Validation of Serpent 2 using experimental data from the SPERT-IV D12/25 Research Reactor Tests
Almachi, J. C.; Sanchez-Espinoza, V. H.
2022. European Research Reactor Conference (RRFM) : Proceedings, 142–150, Karlsruher Institut für Technologie (KIT)

Preliminary results for the C5G7-2D Benchmark using PARAFISH code
Duran-Gonzalez, J.; Sanchez-Espinoza, V. H.; Gomez-Torres, A. M.; Valle-Gallegos, E. del
2022. XXXIII Congreso Anual de la Sociedad Nuclear Mexicana (2022), Veracruz, Mexico, November 13–16, 2022

Determination of the Radiological Consequences by means of JRODOS and JRODOS codes at a generic Akkuyu VVER-1000 plant unit
Mercan, A. K.; Gabrielli, F.; Sanchez-Espinoza, V. H.; Raskob, W.
2022. International Nuclear Sciences and Technologies Conference (INSTEC 2022), Aydin, Turkey, October 19–22, 2022

Assessment of the ASTEC Model of a Generic BWR-4 Mark-1 Peach Bottom Unit-2 NPP and Analysis of the ST-SBO Severe Accident Scenario
Murat, O.; Gabrielli, F.; Sanchez-Espinoza, V. H.; Stieglitz, R.
2022. International Nuclear Sciences and Technologies Conference (INSTEC 2022), Aydin, Turkey, October 19–22, 2022

Assessment of the ASTEC Model of a Generic BWR-4 Mark-1 Peach Bottom Unit-2 NPP and Analysis of the ST-SBO Severe Accident Scenario
Murat, O.; Gabrielli, F.; Sanchez-Espinoza, V. H.; Stieglitz, R.
2022. 11th ASTEC Users Club Meeting (2022), Paris, France, September 28–30, 2022

Radiological Consequences of severe accident scenarios in a generic KONVOI NPP
Gabrielli, F.; Sanchez-Espinoza, V. H.; Pauli, E. M.
2022. 11th ASTEC Users Club Meeting (2022), Paris, France, September 28–30, 2022

Impact of Realistic Fuel Inventories on the Radiological Consequences of a severe accident scenario in a generic KONVOI plant by means of the ASTEC Code
Gabrielli, F.; Stakhanova, A.; Sanchez-Espinoza, V. H.; Pauli, E. M.; Hoefer, A.; Feldmann, H.
2022. Jahrestagung Kerntechnik (2022), Leipzig, Germany, June 21–22, 2022

High-fidelity pin-by-pin analysis of the rostov-2 Core using serpent2/Subchanflow
Beydogan, N.; Mercatali, L.; Sanchez Espinoza, V.
2022. OECD/NEA 4th Rostov-2 benchmark workshop (2022), Aix-en-Provence, France, May 30–31, 2022

H2020 McSAFER: High-Performance Advanced Methods and Experimental Investigations for the Safety Evaluation of Generic Small Modular Reactors
Sanchez-Espinoza, V. H.; Suikkanen, H.; Valtavirta, V.; Bencik, M.; Kliem, S.; Queral, C.; Farda, A.; Smith, P.; Van Uffelen, P.; Seidl, M.; Schneidesch, C.; Grishchenko, D.; Lestani, H.
2022. 20th Meeting of the Technical Working Group on Fuel Performance and Technology (TWG FPT 2022), Online, April 5–7, 2022

KIT Neutronic Computational Tools for SMR Core Analysis
Sanchez-Espinoza, V. H.; Blanco, J.; Zhang, K.; Campos-Munoz, A.; Duran-Gonzalez, J.; Mercatali, L.; Imke, U.
2022. 4th UPM/CEIDEN Workshop on SIMR Neutronics (2022), Online, May 19, 2022

Coupling of PARCS with the Porous-media two-phase flow code Twoporflow for the imporved analysis of SMR-cores using the IcoCo-Approach
Campos-Munos, A.; Sanchez-Espinoza, V. H.; Imke, U.
2022. CAMP-Spring Meeting (2022), Online, May 17–19, 2022

SMR-Core Analysis at pin-level using PARCS-SP3
Zhang, K.; Sanchez, V.; Mercatali, L.
2022. CAMP-Spring Meeting (2022), Online, May 17–19, 2022

Preliminary Uncertainty and Sensitivity Analysis of the ASTEC simulations results of a MBLOCA scenario at a Generic KONVOI Plant using FSTC tool
Stakhanova, A.; Gabrielli, F.; Sanchez-Espinoza, V. H.; Pauli, E.; Hoefer, A.
2022. 10th European Review Meeting on Severe Accident Research (ERMSAR 2022), Karlsruhe, Germany, May 16–19, 2022

First outcomes from the PHEBUS FPT1 uncertainty application done in the EU MUSA project
Mascari, F.; Bersano, A.; Massone, M.; Agnello, G.; Coindreau, O.; Beck, S.; Tiborcz, L.; Paci, S.; Angelucci, M.; Herranz, L. E.; Bocanegra, R.; Pontillon, Y.; Wang, H.; Pingwen, O. U.; Zhenzhen, G. E.; Berdai, M.; Cherednichenko, O.; Iskra, A.; Nudi, M.; Groudev, P.; Petrova, P.; Kretzschmar, F.; Gabrielli, F.; Zhang, K.; Vileiniskis, V.; Kaliatka, T.; Lilin, D.; Kalilainen, J.; Malicki, M.; Shengqin, G.; Gumenyuk, D.; Vorobyov, Y.; Kotsuba, O.; Dejardin, P.; Di Giuli, M.; Thomas, R.; Ivanov, I. V.; Giannetti, F.; D’Onorio, M.; Caruso, G.; Salay, M.; Sevon, T.
2022. Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), American Nuclear Society (ANS)

First outcomes from the PHEBUS FPT1 uncertainty application done in the EU MUSA project
Mascari, F.; Bersano, A.; Massone, M.; Agnello, G.; Coindreau, O.; Beck, S.; Tiborcz, L.; Paci, S.; Angelucci, M.; Herranz, L. E.; Bocanegra, R.; Pontillon, Y.; Wang, H.; Pingwen, O. U.; Zhenzhen, G. E.; Berdai, M.; Cherednichenko, O.; Iskra, A.; Nudi, M.; Groudev, P.; Petrova, P.; Kretzschmar, F.; Gabrielli, F.; Zhang, K.; Vileiniskis, V.; Kaliatka, T.; Lilin, D.; Kalilainen, J.; Malicki, M.; Shengqin, G.; Gumenyuk, D.; Vorobyov, Y.; Kotsuba, O.; Dejardin, P.; Di Giuli, M.; Thomas, R.; Ivanov, I. V.; Giannetti, F.; D’Onorio, M.; Caruso, G.; Salay, M.; Sevon, T.
2022. 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19 2022), Brussels, Belgium, March 6–11, 2022

2021

Employment of the ASTEC Code in the severe accidents research activities at KIT
Gabrielli, F.; Sanchez Espinoza, V. H.; Murat, O.; Mercan, A. K.; Tromm, W.
2021. NENE2021 Conference Proceedings. Ed.: L. Cizelj, Art.-Nr. 413, Nuclear Society of Slovenia

The MUSA Project management and uncertainties of severe accidents
Mascari, F.; Sanchez-Espinoza, V. H.
2021. Eurosafe (2021), Paris, France, November 22–23, 2021

Multiscale thermal-hydraulic methods for improved simulation of nuclear power plants
Sanchez-Espinoza, V.; Zhang, K.; Böttcher, M.
2021. OECD/NEA/CSNI Specialists meeting on Transient Thermal-Hydraulics in Water cooled nuclear Reactors (SM-TH 2021), Madrid, Spain, December 14–17, 2021

Thermo hydraulic modelling needs for LWR-SMRs
Queral, C.; Sanchez-Espinoza, V.; Giménez, M.; Zanocco, P.; Alzaben, Y.; Sanchez-Torrijos, J.; Fernandez-Cosials, K.
2021. OECD/NEA/CSNI Specialists meeting on Transient Thermal-Hydraulics in Water cooled nuclear Reactors (SM-TH 2021), Madrid, Spain, December 14–17, 2021

Direct calculation of safety-related parameters for coupled transients using Monte Carlo Neutronics plus subchannel thermal-hydraulics
Ferraro, D.; Garcia, M.; Valtavirta, V.; Imke, U.; Tuominen, R.; Leppänen, J.; Sanchez-Espinoza, V. H.
2021. Proceedings of the Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, 549–558, American Nuclear Society (ANS)

High-fidelity analysis of MTR core using serpent 2/ SubChanFlow
Almachi, J. C.; Sanchez, V. H.; Imke, U.; Mercatali, L.
2021. European Research Reactor Conference Proceedings

Employment of the ASTEC Code in the severe accidents research activities at KIT
Gabrielli, F.; Sanchez Espinoza, V. H.; Mercan, A. K.; Tromm, W.
2021. 30th International Conference Nuclear Energy for New Europe (NENE 2021), Bled, Slovenia, September 6–9, 2021

High-performance advanced methods and experimental investigations for the safety evaluation of generic small modular reactors: The H2020 Mcsafer project
Sanchez-Espinoza, V. H.; Gabriel, S.; Suikkanen, H.; Telkkä, J.; Valtavirta, V.; Bencik, M.; Kliem, S.; Queral, C.; Farda, A.; Abeguile, F.; Smith, P.; Van Uffelen, P.; Ammirabile, L.; Seidl, M.; Schneidesch, C.; Grishchenko, D.; Lestani, H.
2021. Proceedings of the 28th International Conference on Nuclear Engineering, 64834, The American Society of Mechanical Engineers (ASME). doi:10.3030/945063

Thermal-hydraulic analysis of a VVER-1000/V-320 reactor with TRACE5p5 code
Redondo-Valero, E.; Queral, C.; Sanchez-Espinoza, V.
2021. Proceedings of the European Nuclear Young Generation Forum ENYGF’21

Analisis tremohidraulico de secuencias accidentales en un reactor VVER-1000/V-320 con el codigo TRACESP2
Redondo Valero, E.; Queral, C.; Sanchez Espinoza, V.
2021. Proceedings of the Annual meeting of the Spanish Nuclear Soceity (SNE)

Codes and methods improvements for vver comprehensive safety assessment: The CAMIVVER H2020 project
Verrier, D.; Vezzoni, B.; Calgaro, B.; Bernard, O.; Previti, A.; Lafaurie, C.; Hashymov, A.; Groudev, P.; Stefanova, A.; Zaharieva, N.; Damian, F.; Mosca, P.; Tomatis, D.; Bieder, U.; Willien, A.; Dos Santos, N.; Mercatali, L.; Sanchez-Espinoza, V. H.; Forgione, N.; Paci, S.
2021. Proceedings of the 28th International Conference on Nuclear Engineering, V002T07A010, The American Society of Mechanical Engineers (ASME). doi:10.1115/ICONE28-64169

High-fidelity analysis of MTR core using serpent 2/ SubChanFlow
Almachi, J. C.; Sanchez, V. H.; Imke, U.; Mercatali, L.
2021. European Research Reactor Conference (RRFM 2021), Helsinki, Finland, September 24–29, 2021

2020

Multi-Scale Coupling of TRACE and TrioCFD Based on ICoCo
Zhang, K.; Zhang, X.; Sanchez-Espinoza, V. H.; Stieglitz, R.
2020. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019), 5165–5178, American Nuclear Society (ANS)

The ICoCo based coupling of TRACE and SCF in SALOME, and a new function of TRACE: an automatic connection between Cylinder and Cartesian VESSELs instead of using the VESSEL JUNCTION component in SNAP
Zhang, K.
2020. Code Application and Maintenance Program (CAMP 2020), Online, November 4–6, 2020

The McSafe project - high-performance monte carlo based methods for safet demonstration: from Proof of concept to industry applications
Sanchez-Espinoza, V.; Mercatali, L.; Leppänen, J.; Hoogenboom, E.; Vocka, R.; Dufek, J.
2020. PHYSOR 2020: Transition to a Scalable Nuclear Furture

Serpent/SUBCHANFLOW coupled calculations for a VVER Core at hot full power
Ferraro, D.; Garcia, M.; Imke, U.; Valtavirta, V.; Tuominen, R.; Bilodid, Y.; Leppänen, J.; Sanchez-Espinoza, V.
2020. PHYSOR 2020: Transition to a Scalable Nuclear Future

Serpent/Subchanflow coupled burnup calculations for VVER fuel Assemblies
Ferraro, D.; Garcia, M.; Imke, U.; Valtavirta, V.; Tuominen, R.; Leppänen, J.; Sanchez-Espinoza, V.
2020. PHYSOR 2020: Transition to a Scalable Nuclear Future. doi:10.1051/epjconf/202124704005

Serpent2-SUBCHANFLOW-TRANSURANUS pin-by-pin depletion calculations for a PWR fuel assembly
Garcia, M.; Tuominen, R.; Gommlich, A.; Ferraro, D.; Valtavirta, V.; Imke, U.; Van Uffelen, P.; Mercatali, L.; Sanchez-Espinoza, V.; Leppänen, J.; Kliem, S.
2020. Physor2020: Transition to a Scalable Nuclear Future

A subchannel coarsening method for Serpent2-SUBCHANFLOW applied to a full-core VVER problem
Garcia, M.; Ferraro, D.; Valtavirta, V.; Tuominen, R.; Imke, U.; Mercatali, L.; Sanchez-Espinoza, V.
2020. Physor2020: Transition to a Scalable Nuclear Future. doi:10.1051/epjconf/202124706018

Extension of subchanflow for thermal hydraulic analysis of MTR-core
Almachi, J. C.; Imke, U.; Sanchez-Espinoza, V. H.
2020. European Research Reactor Conference (2020), Online, October 12–15, 2020

Specific Aspects of Reactor Safety Research at KIT
Gabrielli, F.; Sanchez-Espinoza, V. H.; Stieglitz, R.; Tromm, W.
2020. Workshop “Convergent Research in the Design of a Modern and Resilient Grid“ (2020), Charlotte, NC, USA, March 2–5, 2020

2019

Implementation of the System Thermal-Hydraulic code TRACE into SALOME Platform for Multi-Scale Coupling
Zhang, K.; Sanchez-Espinoza, V.; Stieglitz, R.
2019. 50th Annual Meeting on Nuclear Technology (AMNT 2019). CD-ROM, INFORUM Verlags- und Verwaltungsgesellschaft mbH

Serpent and Tripoli-4® transient calculations comparisons for several reactivity insertion scenarios in a 3D PWR minicore benchmark
Ferraro, D.; Sanchez-Espinoza, V.; Faucher, M.; Mancusi, D.; Zoia, A.; Valtavirta, V.; Leppänen, J.
2019. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, 1734–1743, American Nuclear Society (ANS)

Advanced Modelling capabilities for pin-level subchannel analysis of PWR and VVER reactors
Garcia, M.; Imke, U.; Ferraro, D.; Sanchez-Espinoza, V.; Mercatali, L.
2019. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), 4299–4309, ANS

Development of an Object-oriented Serpent2-SUBCHANFLOW Coupling and Verification with Problem 6 of the VERA Core Physics Benchmark
Garcia, M.; Ferraro, D.; Valtavirta, V.; Imke, U.; Tuominen, R.; Sanchez-Espinoza, V.; Mercatali, L.
2019. International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2019), 1424–1433, American Nuclear Society (ANS)

High-fidelity multiphysics simulations for Light Water Reactors in the McSAFE H2020 project
Mercatali, L.; Sanchez-Espinoza, V. H.; Garcia, M.; Ferraro, D.; Imke, U.; Leppänen, J.; Valtavirta, V.; Kliem, S.; Van Uffelen, P.
2019. AAA Workshop: Abbrand, Abschirmung, Aktivierung (2019), Garching bei München, Germany, December 2, 2019

Serpent and TRIPOLI-4® transient calculations comparisons for several reactivity insertion scenarios in a 3D PWR minicore benchmark
Ferraro, D.; Faucher, M.; Mancusi, D.; Zoia, A.; Valtavirta, V.; Leppänen, J.; Sanchez-Espinoza, V.
2019. International Conference on Mathematics and Computational Methods (M&C 2019), Portland, OR, USA, August 25–29, 2019

Development of an Object-oriented Serpent2-SUBCHANFLOW Coupling and Verification with Problem 6 of the VERA Core Physics Benchmark
Garcia, M.; Ferraro, D.; Valtavirta, V.; Imke, U.; Tuominen, R.; Sanchez-Espinoza, V.; Mercatali, L.
2019. International Conference on Mathematics and Computational Methods (M&C 2019), Portland, OR, USA, August 25–29, 2019

Advanced multi-physics modelling activities within the EU McSAFE project
Sanchez-Espinoza, V. H.; Mercatali, L.; Leppänen, J.; Hoogenboom, E.; Vocka, R.; Dufek, J.
2019. OECD/NEA Second Multi-Physics Model Validation Workshop (MPMV 2019), Garching bei München, Germany, June 26–28, 2019

KIT multi-physics developments for reactor analysis
Sanchez, V.; Imke, U.; Mercatali, L.; Abalkhail, A.
2019. OECD/NEA Second Multi-Physics Model Validation Workshop (MPMV 2019), Garching bei München, Germany, June 26–28, 2019

Multi-Scale Coupling of TRACE and TrioCFD Based on ICoCo
Zhang, K.; Zhang, X.; Sanchez-Espinoza, V. H.; Stieglitz, R.
2019. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019), Portland, OR, USA, August 18–23, 2019

Implementation of the System Thermal-Hydraulic code TRACE into SALOME Platform for Multi-Scale Coupling
Zhang, K.; Sanchez-Espinoza, V.; Stieglitz, R.
2019. 50. Jahrestagung Kerntechnik (2019), Berlin, Germany, May 7–8, 2019

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.
2019. 9th European Commission Conference on EURATOM Research and Training in Safety of Reactor Systems and Radioactive Waste Management (FISA / EURADWASTE 2019), Piteşti, Romania, June 4–7, 2019

McSAFE – High Performance Monte Carlo Methods for SAFEty Demonstration
Sánchez, V.; Mercatali, L.; Dufek, J.; Leppanen, J.; Hoogenboom, E.; Vocka, R.
2019. NUGENIA Forum (2019), Paris, France, March 13–15, 2019

2018

Development of a Spatial Domain Decomposition Scheme for Monte Carlo Neutron Transport
García, M.; Ferraro, D.; Sanchez-Espinoza, V. H.; Mercatali, L.; Leppänen, J.; Valtavirta, V.
2018. Proceedings of the 26th International Conference on Nuclear Engineering. Vol 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A042, The American Society of Mechanical Engineers (ASME). doi:10.1115/ICONE26-82144

Propagation of Nuclear Data Uncertainties in PWR Pin-Cell Burnup Calculations via Stochastic Sampling
Mercatali, L.; Alzaben, Y.; Sanchez Espinoza, V. H.
2018. 26th International Conference on Nuclear Engineering, ICONE 2018; London; United Kingdom; 22 July 2018 through 26 July. Vol. 3, The American Society of Mechanical Engineers (ASME). doi:10.1115/ICONE26-81711

Integral Smart Plant Model Developed for the System Thermal Hydraulic Code Trace for Transient Analysis
Sanchez-Espinoza, V. H.; Marin, V. M.; Alzaben, Y.; Jimenez, G.; Stieglitz, R.
2018. 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Nuthos-12), Qingdao, China, October, 14-18, 2018. Proceedings on CD-ROM, Paper 574

Multi-Scale Coupling of TRACE and SUBCHANFLOW based on ECI for the Analysis of 3D Phenomena inside the PWR RPV
Zhang, K.; Sanchez Espinoza, V. H.
2018. 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (Nuthos-12), Qingdao, China, October, 14-18, 2018. Proceedings on CD-ROM, Paper 552

KIT Numerical and Experimental Investigations for LWR Reactor Safety
Sanchez-Espinoza, V. H.; Stieglitz, R.; Tromm, W.
2018. Universidad Politecnica de Madrid (2018), Madrid, Spain, December 4, 2018

Foreseen capabilities, bottlenecks identification and potential limitations of serpent mc transport code in large-scale full 3-D burnup calculations
Ferraro, D.; Garcia, M.; Mercatali, L.; Sanchez Espinoza, V. H.; Leppänen, J.; Valtavirta, V.
2018. 2018 26th International Conference on Nuclear Engineering, ICONE 2018; London; United Kingdom; 22 July 2018 through 26 July 2018, 9 p., The American Society of Mechanical Engineers (ASME). doi:10.1115/ICONE26-82305

McSAFE - High Performance Monte Carlo Methods for SAFEty Demonstration
Sacnhez, V.; Mercatali, L.; Malvagi, F.; Smith, P.; Dufek, J.; Seidl, M.; Milisdorfer, L.; Leppanen, J.; Hoogenboom, E.; Kliem, S.; Van Uffelen, P.; Kerkar, N.
2018. 28th Symposium of AER on VVER Reactor Physics and Reactor Safety (2018), Olomouc, Czechia, October 9–12, 2018

Multi-Scale Coupling of TRACE and SUBCHANFLOW based on ECI for the Analysis of 3D Phenomena inside the PWR RPV
Zhang, K.; Sanchez Espinoza, V. H.
2018. 12th International Topical Meeting on Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS 2018), Qingdao, China, October 14–18, 2018

Foreseen capailities, bottlenecks identification and potential limitations of serpent MC transport code in large-scale full 3-D burnup calcualtions
Ferraro, D.; Garcia, M.; Mercatali, L.; Sanchez, V.; Leppänen, J.; Valtavirta, V.
2018. 26th International Conference on Nuclear Engineering (ICONE 2018), London, United Kingdom, July 22–28, 2018

Development of a Spatial Domain Decomposition Scheme for Monte Carlo Neutron Transport
Garcia, M.; Ferraro, D.; Mercatali, L.; Sanchez, V.; Leppänen, J.; Valtavirta, V.
2018. 26th International Conference on Nuclear Engineering (ICONE 2018), London, United Kingdom, July 22–28, 2018

Propagation of nuclear data uncertainties in PWR pin-cell burnup calculations via stochastic sampling
Mercatali, L.; Alzaben, Y.; Sanchez Espinoza, V. H.
2018. 26th International Conference on Nuclear Engineering (ICONE 2018), London, United Kingdom, July 22–28, 2018

Implementation of TRACE in SALOME Platform for Coupling with open-source CFD codes
Zhang, K.; Sanchez-Espinoza, V. H.
2018. Best Uncertainty Plus Assessment (BEPU 2018), Ottawa, Canada, May 28–30, 2018

McSAFE - High Performance Monte Carlo Methods for SAFEty Demonstration
Sanchez, V.; Mercatali, L.; Malvagi, F.; Smith, P.; Dufek, J.; Seidl, M.; Milisdorfer, L.; Leppanen, J.; Hoogenboom, E.; Vocka, R.; Kliem, S.; Van Uffelen, P.; Kerkar, N.
2018. Nuclear Days and NUGENIA Annual Forum (2018), Prague, Czechia, April 10–12, 2018

Extension of Serpent2/SUBCHANFLOW coupling for hexagonal fuel assemblies
Alzaben, Y.; Ziegahn, C.-R.; Sanchez-Espinoza, V. H.
2018. Physics of Reactors (PHYSOR 2018), Cancún, Mexico, April 22–26, 2018

2017

Implementation and validation of CHF models in the two-phase flow porous media code
Jauregui Chavez, V.; Imke, U.; Jimenez, J.; Sanchez-Espinoza, V.
2017. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi’an, China, September 3-8, 2017.Proceedings on USB-Stick, Paper No.20248

KIT Activities and Infrastructure for Education and Training on Knowledge Management in Reactor Safety and Technology
Sanchez-Espinoza, V. H.; Tromm, W.; Stieglitz, R.
2017. Segundo Simposio International sobre Educacion, Capacitacion, Extension y Gestion del conocimiento en Tecnologia Nuclear, Buenos Aires, ARG, November 13-17, 2017

Titel: Analysis of PWR Severe accident sequences including mitigative measures to prevent or delay the failure of safety barriers with the severe accident code ASTEC
Sanchez Espinoza, V. H.; Gomez-Garcia-Torano, I.
2017. International Conference on Topical Issues in Nuclear Installation Safety: Safety Demonstration of Advanced Water Cooled Nuclear Power Plants, Wien, A, June 6-9, 2017 IAEA-CN-251, IAEA

Titel: Analysis of PWR Severe accident sequences including mitigative measures to prevent or delay the failure of safety barriers with the severe accident code ASTEC
Sanchez Espinoza, V. H.; Gomez-Garcia-Torano, I.
2017. IAEA International Conference on Topical Issues in Nuclear Installation Safety: Safety Demonstration of Advanced Water Cooled Nuclear Power Plants (2017), Vienna, Austria, June 6–9, 2017

Parcs-subchanflow-transuranus multiphysics coupling for improved pwr’s simulations
Basualdo, J. R.; Sánchez-Espinoza, V. H.; Stieglitz, R.; Macián-Juan, R.
2017. International Congress on Advances in Nuclear Power Plants (ICAPP 2017), Fukui and Kyoto, J, April 24-28, 2017. Proceedings on CD-ROM, Atomic Energy Society of Japan

PARCS-SUBCHANFLOW-TRANSURANUS multiphysics coupling for high fidelity PWR reactor core simulation: preliminary results
Basualdo, J. R.; Sanchez, V. H.; Stieglitz, R.; Macian-Juan, R.
2017. 48. Jahrestagung Kerntechnik / 48th Annual Meeting on Nuclear Technology (AMNT 2017), Berlin, May 16-17, 2017, CD-ROM, INFORUM Verlags- und Verwaltungsgesellschaft mbH

KIT multi-physics developments for reactor analysis
Sanchez Espinoza, V. H.
2017. 1st KIT-SJTU Student Workshop on Nuclear Engineering (2017), Karlsruhe, Germany, September 10–15, 2017

Reactor safety investigations at KIT with the HGF NUSAFE program
Sanchez, V.; Tromm, W.; Stieglitz, R.
2017. 2nd Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology (SG-FANS), Karlsruhe, September 12-15, 2017

Coupling of TRACE and Subchanflow (SCF) based on the exterior communication interface (ECI)
Zhang, K.; Sanchez Espinoza, V. H.
2017. Oversea Scholars Visit to Chinese Academy of Science, Beijing, China, September 28, 2017

Further development of a thermal-hydraulic two-phase flow tool
Jauregui Chavez, V.; Imke, U.; Jimenez, J.; Sanchez-Espinoza, V. H.
2017. 48. Jahrestagung Kerntechnik / 48th Annual Meeting on Nuclear Technology (AMNT 2017), Berlin, May 16-17, 2017, CD-ROM, INFORUM Verlags- und Verwaltungsgesellschaft mbH

Simulation of KSMR core zero power condidions using the Monte Carlo code Serpent
Alzaben, Y.; Sanchez-Espinoza, V. H.; Stieglitz, R.
2017. 48. Jahrestagung Kerntechnik / 48th Annual Meeting on Nuclear Technology (AMNT 2017), Berlin, May 16-17, 2017, CD-ROM, INFORUM Verlags- und Verwaltungsgesellschaft mbH

ASTEC investigations of accident management measures for a station black-out (SBO) scenario in a generic German konvoi PWR
Sanchez-Espinoza, V. H.; Gomez-Garcia-Torano, I.; Rebollo, M. J.; Kretzschmar, F.
2017. 8th European Review Meeting on Severe Accident Research (ERMSAR), Warszawa, PL, May 16-18, 2017. Proceedings on USB-Stick, Paper 609

High-fidelity MC-based coupled simulations of LWR cores at pin-level
Mercatali, L.; Sanchez, V. H.
2017. 2nd OECD/NEA C5G7 Time-Dependent (TD) Neutron Transport Benchmark Workshop, AREVA, Erlangen, May 11-12, 2017

Updated KIT contribution to UAM PHASE-I
Marcatali, L.; Alzaben, Y.; Sanchez, V.
2017. 11th OECD/NEA Light Water Reactor (LWR) Uncertainty Analysis in Modelling (UAM) Benchmark Workshop, AREVA, Erlangen, May 10-12, 2017

McSAFE - High performance Monte Carlo methods for SAFEty demonstration, From proof of concept to industry-like applications
Sanchez, V.; Mercatali, L.; Malvagi, F.; Smith, P.; Dufek, J.; Seidl, M.; Milisdorfer, L.; Leppanen, J.; Hoogenboom, E.; Vocka, R.; Kliem, S.; Van Uffelen, P.; Kerkar, N.
2017. NUGENIA Annual Forum, Amsterdam, NL, March 28-30, 2017

Neutronics safety-related investigations of a generic SMART core with state-of-the-art tools
Alzaben, Y.; Sanchez, V.; Stieglitz, R.
2017. 11th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-11), Gyeongju, Korea, October 9-13, 2016. Proceedings on USB-Stick, Paper N11A0254

Thermal-hydraulic uncertainty and sensitivity analysis using SUBCHANFLOW and URANIE
Jimenez, J.; Imke, U.; Sanchez Espinoza, V. H.
2017. 48.Jahrestagung Kerntechnik,, Berlin, 16.-17.Mai 2017

2016

Investigations of a BWR SB-LOCA severe Accident scenario including SAM to prevent the reactor pressure vessel failure using the german Code ATHLET-CD
Sanchez Espinoza, V. H.; De Marcello, V.; Imke, U.
2016. 42nd Annual Meeting of Spanish Nuclear Society, Santander, E, September 29-30, 2016

Fukushima Unit 2 Accident Simulation With MELCOR 2.1
Bocanegra, R.; Di Marcello, V.; Sanchez, V.; Jiménez, G.
2016. 2016 24th International Conference on Nuclear Engineering, ICONE 2016; Charlotte; United States; 26 June 2016 through 30 June 2016, V005T15A078, The American Society of Mechanical Engineers (ASME). doi:10.1115/ICONE24-61079

On the use of serpent for SMR modeling and cross section generation
Alzaben, Y.; Sanchez-Espinoza, V. H.; Stieglitz, R.
2016. 6th International Serpent User Group Meeting, Milano, I, September 26-29, 2016

Internal coupling of the code DYN3D with the USNRC code trace- first results
Gonzalez, J.; Sanchez, V.; Jimenez, J.
2016. Proceedings of PHYSOR 2016 : Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho, May 1-5, 2016, 1711–1721, American Nuclear Society (ANS)

Simulation of severe accident management measures for selected lbloca scenarios in a generic pwr konvoi plant using ASTECV2.0
García-Toraño, I. G.; Sánchez, V.; Stieglitz, R.
2016. International Congress on Advances in Nuclear Power Plants, ICAPP 2016; San Francisco; United States; 17 April 2016 through 20 April 2016. Vol. 3, 1870–1878, American Nuclear Society (ANS)

AHLET/COBRA-TF multi-scale thermal-hydraulics analysis of the O2 event within the NURESAFE project
Jimenez, J.; Di Marcello, V.; Sanchez, V.; Perin, Y.
2016. OECD/NEA Oskarshamn-2 5th Workshop, Paul Scherrer Institut, Villigen, CH, May 30-31, 2016

Assessment of the CTF post-CHF models using FEBA experimental data
Perez, J.; Quivy, B.; Schneidesch, C.; Jimenez, J.; Sanchez, V.
2016. CTF User Group Meeting, Paul Scherrer Institut, Villigen, CH, June 1-2, 2016

Internal coupling of the code DYN3D with the USNRC code trace- first results
Gonzalez, J.; Sanchez, V.; Jimenez, J.
2016. PHYSOR 2016 : Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho, May 1-5, 2016

Accelerating AZKIND simulations of light water nuclear reactor cores using PARALUTION on GPU
Rodríguez-Hernandez, A.; Gómez-Torres, A. M.; Valle-Gallegos, E. del; Jimenez-Escalante, J.; Trost, N.; Sanchez-Espinoza, V. H.
2016. High performance computer applications : 6th international conference, ISUM 2015, Mexico City, Mexico, 419–431, Springer. doi:10.1007/978-3-319-32243-8_29

HGF-Activities for liquid metal fast reactor systems
Daubner, M.; Gordeev, S.; Haselbauer, M.; Hering, W.; Jäger, W.; Onea, A.; Pacio, J.; Perez, S.; Ponomarev, A.; Rineiski, A.; Sanchez, V.; Wetzel, T.; Stieglitz, R.; Eckert, S.; Fridman, E.; Gerbeth, G.; Hampel, U.; Kliem, S.
2016. Generation IV International Forum, 14th SFR Safety and Operation PMB Meeting, Karlsruhe, March 15-18, 2016

2015

ATHLET-CD analysis of water injection into a partly-damaged bwr core for accident management improvement
Di Marcello, V.; Sanchez, V.; Imke, U.
2015. 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015, Chiba, Japan, May 17-23 2015, The American Society of Mechanical Engineers (ASME)

KIT-INR contribution to CESAM WP40: Status of ASTEC simulation of a PWR konvoi plant
Gomez Garcia-Torano, I.; Sanchez, V.
2015. CESAM Project 2nd Periodic Workshop, Bologna, I, February 23-26, 2015

Status of KIT contributions to WP3.3
Jimenez, J.; Sanchez, V.
2015. NURESAFE 7th Meeting, Bruxelles, B, November 2-3, 2015

KIT results for the hot assembly BC problem using COBRA-TF and SUBCHANFLOW
Jimenez, J.; Sanchez, V.
2015. NURESAFE 7th Meeting, Bruxelles, B, November 5-6, 2015

KIT results for the nodal based scenarios using DYN3D-COBRA-TF
Jimenez, J.; Sanchez, V.
2015. NURESAFE 7th Meeting, Bruxelles, B, November 5-6, 2015

Severe accident analysis of a SB-LOCA scenario in a 72-type BWR plant with ATHLET-CD
Di Marcello, V.; Sanchez, V.; Imke, U.
2015. 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015

Severe accident analysis of a SB-LOCA scenario in a 72-type BWR plant with ATHLET-CD
Di Marcello, V.; Sanchez, V.; Imke, U.
2015. Proceedings of the 21th International QUENCH Workshop, Karlsruhe, October 27-29, 2015. Hrsg.: M. Steinbrück, Karlsruher Institut für Technologie (KIT)

MYRRHA sub-critical mock-up definition
Mercatali, L.
2015. FREYA Mid-Term Review Meeting, Bruxelles, B, January 27-28, 2015

FREYA WP2: Subcritical configuration for design and licensing of MURRHA/FASTEF. Scope of activity
Mercatali, L.
2015. FREYA Mid-Term Review Meeting, Bruxelles, B, January 27-28, 2015

CESAM: Simulation of a large break LOCA sequence in a German PWR konvoi with the severe accident code ASTEC
Gomez Garcia-Torano, I.; Sanchez, V.; Stieglitz, R.
2015. 46.Jahrestagung Kerntechnik, Berlin, 5.-7.Mai 2015, CD-ROM, INFORUM Verlags- und Verwaltungsgesellschaft mbH

Monte Carlo neutronics investigations of VVER-1000 fuel assemblies
Mercatali, L.; Venturini, A.; Sanchez, V. H.
2015. 46.Jahrestagung Kerntechnik, Berlin, 5.-7.Mai 2015, CD-ROM, INFORUM Verlags- und Verwaltungsgesellschaft mbH

Neutronic modeling of a PWR konvoi type reactor using PARCS with few group cross section generated with SCALE and SERPENT
Basualdo, J.; Sanchez, V.; Stieglitz, R.; Macian-Juan, R.
2015. 46.Jahrestagung Kerntechnik, Berlin, 5.-7.Mai 2015, CD-ROM, INFORUM Verlags- und Verwaltungsgesellschaft mbH

WASA-BOSS: Investigation of the coolability of partly-damaged BWR core by water injection into the RPV
Di Marcello, V.; Imke, U.; Sanchez Espinoza, V. H.
2015. 46.Jahrestagung Kerntechnik, Berlin, 5.-7.Mai 2015

Variance reduction in high resolution coupled Monte Carlo - thermal-hydraulics calculations
Ivanov, A.; Sanchez, V.
2015. 1st Joint International Conference on Mathematics and Computations (M&C), Supercomputing in Nuclear Applications (SNA) and Monte Carlo (MC) Method, Nashville, Tenn., April 19-23, 2015. Proceedings. Vol. 3, 1981–1994, ANS

C19-use and applications of COBRA-TF at KIT
Jimenez, J.; Sanchez, V.
2015. 2nd CTF User Group Meeting, Universidad Politecnica de Madrid, E, May 20-21, 2015

Updated KIT results for the exercise 2 of KALININ3 benchmark
Jimenez, J.; Däubler, M.; Sanchez, V.
2015. AER-D Group Meeting, Universidad Politecnica de Madrid, E, May 18-19, 2015

KIT contribution to UAM PHASE-I: Modelling and updated results
Mercatali, L.; Sanchez, V. H.; Venturini, A.
2015. UAM9 Workshop, Madrid, E, May 20-22, 2015

Status of KIT contribution to the WP1.3 of NURESAFE
Jimenez, J.; Sanchez, V.
2015. NURESAFE Meeting, Paris, F, July 1-2, 2015

Fine mesh preprocessor for COBRA-TF
Jimenez, J.; Sanchez, V.
2015. NURESAFE Meeting, Paris, F, July 1-2, 2015

Status of KIT contributions to WP3.3, Multiscale BWR thermal-hysraulics
Jimenez, J.; Sanchez, V.
2015. 6th NURESAFE Meeting, Lappeenranta, SF, June 11-12, 2015

Towards the development of coupled Monte Carlo / subchannel thermal hydraulic codes for high-fidelity simulation of LWR full cores
Sanchez, V.; Ivanov, A.; Hoogenboom, J. E.
2015. FIRST Joint International Conference on Mathematics and Computations (M&C), Supercomputing in Nuclear Applications (SNA) and Monte Carlo (MC) Method, Nashville, Tenn., April 19-23, 2015

High performance Monte Carlo computing projects: from HPMC to McSAFE
Sanchez, V.; Ivanov, A.; Mercatali, L.; Hoogenboom, E.; Dufek, J.; Travleev, A.; Leppänen, J.
2015. NUGENIA Forum 2015, Ljubljana, SLO, April 13-15, 2015

Towards the development of coupled Monte Carlo / subchannel thermal hydraulic codes for high-fidelity simulation of LWR full cores
Sanchez, V.; Ivanov, A.; Hoogenboom, J. E.
2015. 1st Joint International Conference on Mathematics and Computations (M&C), Supercomputing in Nuclear Applications (SNA) and Monte Carlo (MC) Method, Nashville, Tenn., April 19-23, 2015. Proceedings, 1968–1980, ANS

Variance reduction in high resolution coupled Monte Carlo - thermal-hydraulics calculations
Ivanov, A.; Sanchez, V.
2015. FIRST Joint International Conference on Mathematics and Computations (M&C), Supercomputing in Nuclear Applications (SNA) and Monte Carlo (MC) Method, Nashville, Tenn., April 19-23, 2015

Professional education in the framework of gentle
Konings, R. M.; Kloosterman, J. L.; Manara, D.; Sanchez, V. H.; Ricotti, M.; Tamboer, R.; Hyvärinen, J.; Tkaczyk, A.
2015. International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, F, May 3-6, 2015

Coupled MCNP - SAS-SFR calculations for sodium fast reactor core at steady-state
Ponomarev, A.; Travleev, A.; Pfrang, W.; Sanchez, V.
2015. International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, F, May 3-6, 2015

ASTEC code development, validation and applications for severe accident management within the CESAM European project
Van Dosselaere, J. P.; Chatelard, P.; Chevalier-Jabet, K.; Nowack, H.; Herranz, L. E.; Pascal, G.; Sanchez-Espinoza, V. H.
2015. International Congress on Advances in Nuclear Power Plants (ICAPP 2015), Nice, F, May 3-6, 2015

Monte Carlo neutronics investigations of VVER-1000 fuel assemblies
Mercatali, L.; Venturini, A.; Sanchez, V. H.
2015. 46.Jahrestagung Kerntechnik, Berlin, 5.-7.Mai 2015

NURESAFE WP1.4. Status of KIT contribution
Jimenez, J.; Sanchez, V.
2015. 5th NURESAFE Meeting (2015), Prague, Czechia, February 17–18, 2015

NURESAFE WP1.3. Status of KIT contribution
Jimenez, J.; Sanchez, V.
2015. 5th NURESAFE Meeting (2015), Prague, Czechia, February 17–18, 2015