Participation in the project for the Spanish Nuclear Regulatory Body (CSN) titled “Advanced thermal-hydraulics and neutronics and uncertainty treatment in accident analysis” during the 2015–2018 period:
“Uncertainty Analysis of the 35% Reactor Inlet Header Break in a CANDU 6 Reactor using RELAP/SCDAPSIM/MOD4.0 with the Integrated Uncertainty Analysis Option” by Pericas R., Allison C. M., Hohorst J. K., under the topic “RELAP/SCDAPSIM Fukushima related activities”. Presented at The 17th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-17, September. Links: https://inis.iaea.org/search/search.aspx?orig_q=RN:47071245 and http://toc.proceedings.com/41410webtoc.pdf.
“Modeling approach regarding new safety perspectives for CANDU-6 reactor employing RELAP/SCDAPSIM” by Pericas R., Allison C. M., Nistor-Vlad R.M., Dupleac D., Prisecaru I., presented at the 6th International Workshop on "PHWR Challenging Issues for Safe Operation and Long-term Sustainability”, CANSAS 2017, Haiyan, China, November 2017.
“Acoplamiento y Simulación de Difusión Neutrónica y Termo-Fluido en el Reactor ELFR” by Heriberto Sánchez Mora, Juan Luis François Lacouture, Sergio Quezada García, Marco Polo, Pericas R., presented at the XX Congreso Anual de la Sociedad Nuclear Mexicana, Aplicaciones pacíficas de la energía nuclear en beneficio de México, Monterrey, Nuevo León, August 2019.
“Sensitivity Analyses of a hypothetical 6 inch break, LOCA in Ascó NPP using RELAP/MOD3.2” by Pericas R., Reventós F., Batet Ll., published as NUREG/IA-243, 2007.
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”
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
Pericas R.; Ivanov K.; Reventós F.; Batet Ll “Code improving and validation for Asco-II nuclear power plant model using coupled 3D neutron kinetics / thermal-hydraulic code” Journal paper. Annals of Nuclear Energy, Volume 87, Part 2, January 2016, Pages 366–374
Pericas R.; Ivanov K.; Reventós F.; Batet Ll “Comparison of Best Estimate Plus Uncertainties and Conservative Methodologies for a PWR MSLB Analysis Using Coupled 3D Neutron Kinetics/Thermal-Hydraulic Code” Journal paper. UNCT Nuclear Technology, Pages 193-201 | Received 11 Oct 2016, Accepted 20 Feb 2017, Published online: 04 May 2017
Lecturer and Technical consultant expert “Reactor Kinetics training course” and “GSAN and SAET” IAEA, July 2016 Amman, Jordan.
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
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)
