Background

Enso team has more than 15 years experience on Deterministic Codes.

SAFETY ANALYSIS AND SYSTEM CODES VALIDATION & VERIFICATION

Projects

  • Participation as RELAP5 TH analyst in OECD/NEA RBHT project
  • Participation as RELAP5/TRACE TH analyst in OECD/NEA ETHARINUS project
  • Participation as RELAP5/TRACE TH analyst in OECD/NEA PKL-4, PKL-3, PKL-2, PKL-1 projects
  • Participation as RELAP5/TRACE TH analyst in OECD/NEA ROSA-2, ROSA-1 projects
  • Participation as RELAP5/TRACE TH analyst in OECD/NEA ATLAS-2 project
  • Participation and coordination of specific phases on OECD/NEA BEMUSE project
  • Participation in the OECD/NEA UAM-LWR project
  • Contributor in the OECD Scaling State Of the Art Report
  • Participation and coordination of OECD PREMIUM benchmark
  • Support to Ascó-1, Ascó-2 and Vandellós-2 NPP (UPC-ANAV agreement 2008-2011)
  • Project for the Spanish Nuclear Regulatory Body (CSN) “Termohidráulica y neutronica avanzadas y tratamiento de incertidumbres en análisis de accidentes”, 2015-2018.
  • Participation in USNRC CAMP project for V&V activities of RELAP5 and TRACE

Publications and reports

Journals

International meetings & conferences

  • NURETH-18 I
  • NUTHOS-11 I
  • NUTHOS-11 II
  • NURETH-17 I
  • NURETH-16 I
  • NURETH-16 II
  • Topsafe 2008
  • ICCNS-12 I
  • ERMSAR 2019
  • NURETH-14
  • Pericas R.; Allison C. M; Hohorst J. K; “RELAP/SCDAPSIM Fukushima related activities”. The 17th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-17; September  http://toc.proceedings.com/41410webtoc.pdf
  • Pericas R.; Allison C. M; Nistor-Vlad R.M; Dupleac D; Prisecaru I; “Modeling approach regarding new safety perspectives for CANDU-6 reactor employing RELAP/SCDAPSIM”. 6th International workshop on «PHWR Challenging Issues for Safe Operation and Long-term Sustainability” CANSAS 2017 Haiyan, China November 2017.
  • Heriberto Sánchez Mora; Juan Luis François Lacouture; Sergio Quezada García; Polo, Marco; Pericas R; “Acoplamiento y Simulación de Difusión Neutrónica y Termo-Fluido en el Reactor ELFR”. XX Congreso Anual de la Sociedad Nuclear Mexicana Aplicaciones pacíficas de la energía nuclear en beneficio de México Monterrey, Nuevo León, August 2019.

USNRC International Agreement reports

TH-NK COUPLING

Projects

  • Project management & code development of NIRK3D (Neutronic interface for coupling 3D kinetics codes with RELAP5/SCDAPSIM MOD3.X and MOD4.X versions)
  • Project management & code development of 3DKIN (3D kinetics package fully integrated in RELAP5/SCDAPSIM MOD3.X and MOD4.X versions)
  • Integration of RELAP5/SCDAPSIM in OSCAR-5 code

Education and training

  • Master of Nuclear Engineering at the Technical University of Catalonia (UPC, Spain): Teaching neutron kinetics and reactor physics topics applied to PARCS code.
  • Raimon Pericas Ph.D. on Nuclear Engineering at the Technical University of Catalonia (UPC, Spain) with international mention jointly with the Pennsylvania State University (Penn State University, USA) “Contribution to the validation of best estimate coupled codes for the analysis of NK-TH nuclear transients”

Publications

Journals

International meetings

  • IMECE 2015 No 52991
  • IMECE 2015 No 57441
  • NUTHOS-11 3DKIN
  • Pericas R.; Reventós F.; Batet Ll “Improving Neutron Kinetics and Thermal Hydraulics coupled tools for BEPU calculations” paper and poster presentation. 41 reunión anual de la sociedad nuclear española. A Coruña, SPAIN, September 2015

International Workshops

  • Coupling Workshop Mumbai 2018
  • Lecturer and Technical consultant expert “Reactor Kinetics training course” and “GSAN and SAET” IAEA, July 2016 Amman, Jordan.

SEVERE ACCIDENT

Projects

  • Responsible of ISS-JAEA Fukushima technical support project
  • Assessment and prediction of Fukushima core status by using RELAP/SCDAPSIM
  • Modelling of Fukushima spent fuel pool under IAEA project
  • Fukushima analysis of Units 1 and 3
  • Leading code development of SCDAP severe accident code along with Dr. Allison (2011-Present)
  • «Assessment of FRAPCON Capabilities for Prediction of Nuclear Fuel Behavior in Advanced Burners” https://www.ne.ncsu.edu/rdfmg/research/previous-research/
  • Lecturer for RELAP/SCDAP code course for Severe Accident Analysis 25th of March to 12rd of April 2013, The Tsinghua University, Beijing, China
  • Technical consultant expert: JAEA Severe accident management group August-September 2016, O-Arai, Japan (Post Fukushima severe accident analysis)
  • Collaboration with the University of Bucharest on CANDU SA code and model development.
  • Collaboration with McMaster university for CANDU SA code development
  • Lecturer and Chairman on the Severe Accident meeting post Fukushima analysis and lessons learn from it. May 2016. Puerto Vallarta Mexico
  • Technical consultant expert: JAEA Severe accident management group, O-Arai, Japan January 2016 (Post Fukushima severe accident analysis)
  • Teaching RELAP/SCDAP code course for Thermalhydraulics, Severe Accident Analysis and Model developer, July 2015, ISS, NECSA facilities SAFARI reactor, Pretoria, South Africa
  • Teaching RELAP/SCDAP code course for Severe Accident Analysis, February 2017, ISS, Amman, Jordan

Publications

Journals

International meetings

  • ICONE-26 No 81912
  • NURETH-16 No 5996
  • ICONE-26 No 82241
  • Pericas R.; Allison C. M; Hohorst J. K; “RELAP/SCDAPSIM Fukushima related activities”. The 17th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-17; September http://toc.proceedings.com/41410webtoc.pdf
  • Pericas R.; Allison C. M; Hohorst J. K; “RELAP/SCDAPSIM Fukushima related activities”. International Symposium on Advances in Nuclear Engineering, PIEAS Islamabad, Pakistan; October 2018.
  • Pericas R.; Allison C. M; Hohorst J. K; “RELAP/SCDAPSIM Fukushima related activities”. International Topical Workshop on Fukushima Decommissioning Research May 24-26, 2019. J-Village, Naraha, Fukushima.
  • Chris Allison, Judith K. Hohorst, Brian Allison, Damir Konjarek, Tomislav Bajs, R. Pericas, Francesc Reventós and Ramon Lopez «Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM» Science and Technology of Nuclear Installations, 2012
  • Lecturer at SAAM-2013 (Severe Accident Analysis and Management) Symposium “Impact of International Severe Accident Research Programs on Fukushima Daiichi” 1st to 3rd of February 2013, Kanpur, India.

CODE DEVELOPMENT IN NEW REACTOR DESIGNS & ALTERNATIVE FLUIDS

Projects

  • RELAP5/SCDAP/MOD4 code modification and benchmarking for transient accident scenarios of Liquid Metal Test Blanket Systems. Collaboration between UPC and Institute for Plasma Research (India). 2014-2015
  • ISS ITER technical support projects
  • ISS SINAP technical support project (molten salt pebble bed reactor)
  • ISS McMaster technical support projects (Supercritical reactor)
  • ISS technical support for CANDU
  • ISS technical support for Waseda
  • RELAP5/SCDAP/MOD4 code development for new fluids. Implementation of themodynamic and transport properties, and wall-to-fluid heat transfer correlations (Na liquid metal and molten salts)                    

Publications

Journals

International meetings

SIMULATORS AND DATA POST-PROCESSING

Projects

  • Project management and code development of RTSIM (Real Time SIMulator interface) for RELAP5/SCDAPSIM/MOD3.x
    • Integration to CNPO RINSIM simulator
  • Integration to to NEL Td. GRAPE simulation software
  • Technical support to RELAP/SCDAPSIM users for data-post processing
  • Nucleoelectrica-Argentina for Atucha NPP
  • Instituto Nacional de Investigaciones Nucleares for Laguna Verde NPP
  • NECSA for SAFARI research reactors
  • ESKOM for Koeberg NPP
  • Technical support to RELAP/SCDAPSIM users for Severe Accident analysis (JAEA), Jordan
  • Technical support to RELAP/SCDAPSIM users for Severe Accident analysis (KAERI), South Korea
  • Technical support to RELAP/SCDAPSIM users for Safety Analysis, Severe Accident and VVER type reactors for University of Alexandria, Egypt
  • Technical support to RELAP/SCDAPSIM users for Safety Analysis for INVAP, Argentina

Publications

International meetings and conferences