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