Curriculum Vitae Dr.-Ing. Víctor Hugo Sánchez Espinoza

Transcription

1 Curriculum Vitae Dr.-Ing. Víctor Hugo Sánchez Espinoza A Personal Data Family and first name Sanchez Espinoza, Victor Hugo Date of birth Place of birth Agua Blanca in Cajamarca, Perú Nationality German Address: Albert-Schweitzer-Str-19, Stutensee Germany Telefone: victor.sanchez@kit.edu B. Professional Information Project Leader and Deputy Group Leader Senior Scientist Senior Scientist Research Assistant Research Associate Karlsruhe Institute of Technology (KIT) Institute for Neutron Physics and Reactor Technology (INR) Group: Reactor Physics and Dynamics (RPD) Karlsruhe Research Center (FZK) Institute for Nuclear Safety (IRS) Division: Neutron Physics and Reactor Technology Work Area: Multiphysics Methods for Reactor Dynamic and Safety Karlsruhe Research Center (FZK) Institute for Nuclear Safety (IRS) Division: Plant Dynamics and System Simulation Work Area: Safety Assessment of LWR and Gen-IV reactors including validation and improvement of bestestimate codes Dresden University of Technology (TUD) Nuclear Engineering Chair Work Area: Severe Accidents Modelling and Simulation of Invessel Phenomena Peruvian Institute of Nuclear Energy (IPEN) Division: Regulatory Authority Work Area: Nuclear Safety- Licensing of a Research Reactor 10/2009- now / /1991-1/1996 4/1988-2/1991 C. Teaching Experience 1

2 Professorship D. Additional Functions and Responsibilities EU Project Coodinator KIT Representative for CAMP KIT Contact Point for the EU Project NURISP Frederic Joliot Otto-Hahn Summer School Karlsruhe Institute of Technology (KIT) Mechanical Engineering Faculty, Institute for Fusion and Reactor Technology (IFRT), Dynamic Nuclear Systems Chair - Nuclear Safety I: Fundamentals - Nuclear Safety II: Safety Assessment of Nuclear Power Plants AREVA Nuclear Professional School (ANPS) Lectures: - Course 08: Neutronic / Thermal Hydraulic Coupled Codes - Course 09: Design Basis Accidents and their Simulation Codes Coordinator of the High Performance Monte Carlo (HPMC) Project International CAMP Program of the US NRC for Qualification of Safety Analysis Codes Technical Responsible for the NURISP Project (European Nuclear Reactor Simulation Platform) Scientific Secretariat of the Frederic Joliot Otto-Hahn (FJOH) Summer School on Nuclear Reactors, Systems and Fuels Member of the KTG Selection 2 Since 2008 Since 2009 Since 2011 Since 2010 Since 2008 Since 2004 German Nuclear Society Since 2003 (KTG) Board Nuclear Safety Branch Senior Advisor Group Member of the Senior Advisor Since 2010 (SAG) of the EU Human Group (SAG) as KIT Representative Resources Observatory (EHRO-N) for the Nuclear Energy Sector International NURETH Member of the Technical Program Since 2008 Conference Committee International NUTHOS Member of the Technical Program Since 2010 Conference Committee IAEA Expert Nuclear Engineering and Safety Since 2012 Consultant on Nuclear Private and public sector Since 2005 Engineering and Nuclear Safety EU KIC InnoEnergy Initiative Innovative Project INEPT KIT Responsible of WP2: Since 2011

3 E. Invited Lectures GLOBAL Conference MATRE-I Material for Innovative Reactors Summer School Annual Meeting of the German Nuclear Society Universidad Politecnica de Madrid Frederic Joliot/Otto Hahn Summer School F. Advisor of Master Student and PhD Students Student Project work Master Students Dissertations Innovative Education and Training in the Nuclear Sector Plenary V, Special III: Safety and Security considering Fukushima Accident Topic: Importance of LWR Bestestimate Safety Calculations for Analysis of Fukushima-like Accidents Tokyo, Japan Topic: Generation II PWR and BWR Belgium Qualification of Coupled Neutronic / Thermal Hydraulic Codes. Hamburg, Germany Course on Thermal Hydraulic System Codes: Topic: Use and Applications of the Program TRACE for VVER Applications Madrid, Spain Safety-related Modelling Challenges in Reactor Fluid Dynamics. Topic: Steam Line Break Transients in PWR Karlsruhe, Germany Nuclear Engineering and Safety- Simulations Nuclear Engineering and Safety- Simulations Nuclear Engineering and Safety- Simulations Since 1996 Since 1996 Since 1996 G. Education Doctoral Thesis Dresden University of Technology (TUD), Nuclear Engineering Chair Theme: Theoretical and experimental investigations of the Criticality Check as method for nuclear material accounting in nuclear reactors. 3 4/1984-4/1987 Master Thesis Nuclear Research Center Rossendorf 11/1983-2/1984

4 Student Research Project Internship University studies University-entrance Diploma Primary- and Secondary School Theme: Development of an Incore- Irradiation Facility for the industrial production of Co-60 Dresden University of Technology (TUD), Nuclear Engineering Chair Theme: Preparation and realization of Rossi- -Experiments on the Research Reactor (AKR-1) Nuclear Research Center Rossendorf Theme: Thermal hydraulic investigations for the irradiation facility of the Rossendorf Research Reactor Dresden University of Technology (TUD) Mechanical Engineering Faculty Nuclear Engineering Herder Institute Leipzig Leipzig, Germany Agua Blanca Peru 2 /1993-7/1993 9/1992-1/1993 8/1979-2/1984 9/1978-6/1979 4/ /1977 H. Languages. Spanish (Mother tongue), German, English I. Selected Publications of the last 5 years I.1. Magazine Papers W. Jäger, V. H. Sánchez, A. Hurtado; Review and proposal for heat transfer predictions at supercritical water conditions using existing correlations and experiments. Nuclear Engineering and Design. Volume 241, Issue 6, June 2011, Pages Jäger, W. Sanchez, V.; Uncertainty and Sensitivity Analysis for the HELIOS Loop within the LACANES Benchmark. Journal of Energy and Power Engineering 5 (2011) S S. Kliem, A. Gommlich, A. Grahn, U.Rohde, J. Schütze, Th. Frank, A. Gomez, V. Sanchez; Development of multi-physics code systems based on the reactor dynamics code DYN3D, Kerntechnik 765/3 pp (2011) V. Sanchez, W. Jäger, M. Böttcher, B. Truong; Investigation of a Coolant Mixing Phenomena within the Reactor Pressure Vessel of a VVER-1000 Reactor with different Simulation Tools. Journal Science and Technology of Nuclear Installations Vol. 2010, Article ID , 14 pages. W. Jäger, V. Sánchez, W. Lischke; Safety Related Investigations of the 4

5 VVER-1000 Reactor Type by the Coupled Code System TRACE/PARCS. Journal of Power and Energy Systems. Vol2. No.2, Japan Society of Mechanical Engineers. V. Sánchez, M. Böttcher; Investigations of the V1CT Benchmark Phase 1 with the Coupled Code System RELAP5/PACRS. Progress of Nuclear Energy 48 (2006) I.2. International Conferences with Peer-Review 2011 V. Sanchez Espinoza and K. Ivanov; Importance of LWR Best-estimate Safety Calculations for Analysis of Fukushima-like Accidents. Invited Paper for Plenary V, Special III: Safety and Security considering Fukushima Accident. Proceedings of GLOBAL Makuhari, Japan, Dec , Sanchez V., Jäger W., Böttcher M., Ivanov K. and Stieglitz R.; Validation and qualification of advanced thermal hydraulic and safety analysis tools for the safety assessment of VVER-1000 Reactors. 7th. International Scientific and Technical Conference on Safety Assurance of NPP with VVER. Podolsk. Russia, May W. Jäger, V. Sanchez, On the evaluation of the pressure losses in a lead bismuth eutectics cooled fuel assembly with TRACE and SUSA. The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14). Log Number: 009. Hilton Toronto Hotel, Toronto, Ontario, Canada, September 25-29, 2011 A. Berkhan, V. Sánchez and U. Imke; Validation of PWR relevant models of SUBCHANFLOW using the NUPEC PSBT Data. The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14). Log Number: 191. Hilton Toronto Hotel, Toronto, Ontario, Canada, September 25-29, 2011 Sanchez, V. Thieme, M., Tietsch W.; Validation and Application of TRACE for the transient analysis of a German BWR plant. The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14). Log Number: 192,.Hilton Toronto Hotel, Toronto, Ontario, Canada, September 25-29, 2011 Ch. Hartmann, V. Sánchez, and W. Tietsch; Analysis of a German BWR Core with TRACE/PARCS using different cross section sets. The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14). Log Number: 043 Hilton Toronto Hotel, Toronto, Ontario, Canada, September 25-29, 2011 J. Pérez M, M. Böttcher, V. Sánchez; VALIDATION OF NEPTUNE CFD TWO PHASE FLOW MODELS USING THE OECD/NRC BFBT BENCHMARK DATABASE. The 14th International Topical Meeting on 5

6 Nuclear Reactor Thermal Hydraulics (NURETH-14). Log Number: 043. Hilton Toronto Hotel, Toronto, Ontario, Canada, September 25-29, Ivanov, V. Sanchez, U. Imke;.Application of a coupled code system NCNP- SUBCHANFLOW to study conventional and innovative PWR fuel assembly types. Jahrestagung Kerntechnik. Berlin Mai Armando Gomez, Victor Sanchez, Uwe Imke, Rafael Macian; DYNSUB: A BEST ESTIMATE COUPLED SYSTEM FOR THE EVALUATION OF LOCAL SAFETY PARAMETER. Jahrestagung Kerntechnik. Berlin Mai 2011 Jäger, W. Sanchez, V., Cheng X., Monti L., Hurtado A. ; Parametric studies by means of uncertainty and sensitivity methods for coupled thermalhydraulic/neutron-physics applications. Jahrestagung Kerntechnik. Berlin Mai Manuel Calleja, Victor Sanchez, Uwe Imke; IMPLEMENTATION OF SUBCHANFLOW IN THE SALOME PLATFORM AND COUPPLING WITH THE REACTOR DYNAMIC CODE COBAYA3. Jahrestagung Kerntechnik. Berlin Mai 2011 J. Perez, M. Böttcher, V. Sanchez; Validation of NEPTUNE CFD Two Phase Flow Models using PSBT Experiments. Jahrestagung Kerntechnik. Berlin Mai V. Sánchez, U. Imke, R. Gomez; SUBCHANFLOW: A Thermal-Hydraulic Sub-Channel Program to Analyse Fuel Rod Bundles and Reactor Cores. 17th Pacific Basin Nuclear Conference. Cancún, Q.R., México, October 24-30, A. Gomez, V. Sanchez, S. Kliem, A. Gommlich; Integration of DYN3D inside the NURESIM Platform. 17th Pacific Basin Nuclear Conference. Cancún, Q.R., México, October 24-30, W. Jaeger, V. H. Sánchez, L. Monti, A. Hurtado; Uncertainty and Sensitivity Analysis for the High Performance Light Water Reactor with TRACE and SUSA. The 8th International Topical Meeting on Nuclear Thermal- Hydraulics, Operation and Safety (NUTHOS-8) N8P0016 Shanghai, China, October 10-14, W. Jaeger, V. H. Sánchez-Espinoza; Uncertainty and Sensitivity Analysis for the HELIOS Loop within the LAcanes benchmark. Proceedings of ICAPP 10 San Diego, CA, USA, June 13-17, Paper W. Jäger, V. Sánchez and R. Macián-Juan; On the Uncertainty and Sensitivity Analysis of Experiments with Supercritical Water with TRACE and SUSA18th International Conference on Nuclear Engineering (ICONE-18). 6

7 May 17 21, Xi an Intern. Conference Center. Xi an, China. U. Imke, V. Sanchez, R. Gomez; SUBCHANFLOW: An empirical knowledge based subchannel code. Annual Meeting on Nuclear Technology. 4-6 may Berlin Germany Jaeger, W., Sánchez Espinoza, V. H., Hurtado, A.; Safety Related Investigations of a LFR Core with the Coupled TRACE/ERANOS System. International Conference on Fast Reactors and Related Fuel Cycles (FR09), Kyoto, Japan, December 7-11, V.H. Sanchez-Espinoza, R. Dörn, W. Jäger, A. Travleev, L. Monti; Neutronics and Thermal Hydraulic Coupling Schemes for Design Improvement of Liquid Metal Fast systems.. The 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13)N13P1138. Kan Marc Thieme, Wolfgang Tietsch, Rafael Macian, Victor Sanchez; Post-test Investigations of BFBT Critical Power Tests with TRACE. 17th International Conference on Nuclear Engineering, ICONE17. July 12-16, 2009, Brussels, Belgium. M. Thieme, W. Tietsch, R. Macian, V. Sanchez; Validation of TRACE using the void Fraction tests of the NUPEC BFBT Facility. International Congress on Advances in Nuclear Power Plants (ICAPP 2009), Tokio, Japan, May 10-14, Paper Wadim Jaeger, Victor H. Sánchez Espinoza, Niko Schneider, Antonio Hurtado; Assessment of Heat Transfer Correlations for Supercritical Water in the Frame of Best-Estimate Code Validation. International Congress on Advances in Nuclear Power Plants (ICAPP 2008), Tokio, Japan, May 10-14, Paper V. Sanchez and A. Al-hamry; Development of a coupling scheme between MCNP and COBTA-TF for the prediction of the Pin-Power of a PWR Fuel Assemblies. International Conference on Mathematics, Computational Methods & Reactor Physics (M&C 2009) Saratoga Springs, New York, May 3-7, 2009, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2009) W. Jaeger, V. Sánchez-Espinoza, A. Hurtado; Investigations of Experiments and Applications with supercritical H2O with the System Code TRACE.- NUTHOS-7: The 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety. Seoul, Korea, October 5-9, L. Monti, Th. Schulenberg, W. Jäger, V. Sanchez-Espinoza; Application and Improvements of the System Code TRACE for HPLWR Core Analysis. 7

8 NUTHOS-7: The 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety. Seoul, Korea, October 5-9, W. Jaeger, V. Sánchez; Influence of oxide layers on the cladding in a liquid lead environment: a comparison between MATRA and TRACE. International Conference on Reactor Physics, Nuclear Power: A Sustainable Resource Casino-Kursaal Conference Center, Interlaken, Switzerland, September 14-19, W. Jaeger, V. H. Sánchez Espinoza, Bo Feng; Analysis of an XADS Target with the System Code TRACE.. IYNC Interlaken, Switzerland, September Paper No V. Sánchez, A. Al-Hamry, C.H. M. Broeders; Development and Qualification of the Coupled Code System COBRA-TF/THREEDANT for the Pin-by-Pin Power Calculation. Proceedings of ICAPP 08.Anaheim, CA USA, June 8-12, Paper V. Sánchez et al; Qualification and Validation of coupled Neutron kinetics / Thermal Hydraulic System Codes. Invited lecture on Coupled Neutron kinetcs/thermal hydraulic Analysis. Annual Meeting on Nuclear Technology KTG May Hamburg. Germany. Thieme, M., W. Tietsch, V. Sánchez; Validation of Heat Transfer of the CHAN-Component in TRACE using BWR Full-size Fine Mesh Bundle Tests. Annual Meeting on Nuclear Technology KTG May Hamburg. Germany V. Sánchez, M. Böttcher, and W. Jäger; Investigations of the VVER-1000 Coolant Transient Benchmark Phase 2 with Coupled Code Systems. The 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12). Sheraton Station Square, Pittsburgh, Pennsylvania, U.S.A. September 30-October 4, W. Jäger, V. Sánchez; Development of a 3D-VVER-1000-RPV-Model for the Investigations of a Coolant Mixing Experiment with the Best-Estimate Code TRACE. Annual Meeting on Nuclear Technology. Karlsruhe, Germany, May 22-24, V. Sánchez, W. Jäger, T. Kozlowski; Qualification of the 3D Thermal- Hydraulics Model of the Code System TRACE Based on plant data. ICAPP 2007: 2007 International Congress on Advances in Nuclear Power Plants, Nice Acropolis, France, May 13-18, W. Jäger, W. Lischke, V. Sánchez; Safety Related Investigations of the VVER-1000 Reactor Type by the Coupled Code System TRACE/PARCS. International Conference on Nuclear Engineering: Nagoya, Japan, April 22-26,

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