Hands on training on NPP simulations: Building up a full model of an SMR (July 2020)

This will be the sixth edition of the training aiming at a transfer of advanced knowledge and best practices in system code modeling for nuclear power plants. The training is organized with the cooperation of Incheon National University and ENSO. Like in 2019, this year edition will focus on the simulation of an SMR reactor. A simplified model of a Light water pressurized SMR will be developed from scratch. The participants will be guided through the process starting by the review of public information that can be found on the literature. Afterwards the full primary and secondary systems will be developed. In the last part of the course, a transient scenario will be configured and the capacity of the necessary safety systems will be evaluated.

The course is recommended to users:

• who can make a simple model for a system code analysis,
• who can modify the existing input by him/herself,
• who want to analyze an integral behavior of nuclear power plant system based on TH system code analyses.
• who need to develop the logic and the control of a nuclear power plant.

We have two premises for this course:

• Learn by doing. From the design drawings to the analysis of the resultsPersonalized support.
• We will have at least one coach every five persons to guarantee this point

Registration is now open

Hands on OpenFOAM CFD simulations for heat and mass transfer in industrial processes

The course is taught in English language by lecturers at the Technical University of Catalonia ( Barcelona).The course objective is to prepare the assistants to bring to practical cases the best practices and guidelines on Computational Fluid Dynamics simulations. Best
practices and guidelines are derived from the CFD fundamentals. The required theoretical background will be provided. Along the course, the case method is used to introduce the CFD fundamentals and
practical approaches. The cases will be related to nuclear technology but the concepts are valid in any other technical field The covered topics are Course Description

1) Diffusive heat transfer
        Introduction to CFD

        Boundary conditions

        The Finite Volume method for diffusion problems

2) Hydrodynamics and turbulence

        The conservative laws of fluid motion
        The Finite Volume method for advection diffusion problems
        Algorithms for pressure velocity coupling

3) Thermal hydraulics diffusive-convective heat transfer
        CFD strategies for temperature velocity coupling

        Finite Volume method for unsteady flows

After the introduction to each case, its fundamentals, modelling and case set up, the instructors will provide indications on how to proceed with the computer simulations Attendees will have time to perform the simulations on their own Eventually common conclusions will be shared and best practices and guidelines for successful simulations will be retrieved.

Registration is now open

Hands on training on NPP simulations: Building up a full model of an SMR (July 2019)

This will be the fifth edition of the training aiming at a transfer of advanced knowledge and best practices in system code modeling for nuclear power plants. The 2019 edition will focus on the simulation of an SMR reactor. A simplified model of a Light water pressurized SMR will be developed from scratch. The participants will be guided through the process starting by the review of public information that can be found on the literature. Afterwards the full primary and secondary systems will be developed. In the last part of the course, a transient scenario will be configured and the capacity of the necessary safety systems will be evaluated.

The course is recommended to users:

• who can make a simple model for a system code analysis,
• who can modify the existing input by him/herself,
• who want to analyze an integral behavior of nuclear power plant system based on TH system code analyses.
• who need to develop the logic and the control of a nuclear power plant.

We have two premises for this course:

• Learn by doing. From the design drawings to the analysis of the resultsPersonalized support.
• We will have at least one coach every five persons to guarantee this point

Registration is now open

Performing Thermal Hydraulic Safety Analysis for Nuclear Power Plants

PWR Transients, DBA and BDBA safety analysis training course (1^st Edition)

This 2018 course is the 1st edition of the training "Performing Thermal Hydraulic Safety Analysis for Nuclear Power Plants". It is held at the Technical University of Catalonia (Barcelona). The target of the course is to enhance the comprehension of Safety Analysis for workers in the industry, young professionals, analysts from regulatory bodies and individuals interested in the field of Safety Analysis. The course is divided in two blocks:

• Safety Analysis Report (SAR) Chapter 15: Design Basis Accidents (DBA).
• Safety Analysis performed in the field of Beyond Design Basis Accidents (BDBA).

This course is partly financed by the European Nuclear Education Network (ENEN). See the course posted on the ENEN website

Hands on training on NPP simulations: achieving steady state conditions and conducting the simulation of thermal hydraulic phenomenology (June 2018)

In 2018, The ‘Hands on training on NPP simulations: achieving steady state conditions and conducting the simulation of thermal hydraulic phenomenology’ aims at a transfer of advanced knowledge and best practices in system code modeling for nuclear power plants. The 2018 edition differs from previous editions in the sense that the contents will focus on the modelling of a full power plant model from the starting day. In addition to general modeling technique for nuclear power plant systems, the course will provide a hands-on training on how to implement proper operation actions to achieve steady-state conditions by using control components of system codes.  In order to enhance the modeling skills of participants, information on important physical phenomena and the best practices in modeling will be given and discussed during the course.

Advanced Thermal-Hydraulic Phenomenology with System Codes. RELAP and TRACE Training (June 2017)

For the third consecutive year, the training “Advanced Simulation of Thermal Hydraulic Phenomenology with system codes” has been held at the Technical University of Catalonia (Barcelona). In this sense,  we are really proud to see how the course has become consolidated during this time. In 2017, we hosted 14 people from 6 different countries: South Korea, People’s Republic of China, South Africa, Republic of Congo, Switzerland and Czech Republic. Participants came from a diverse origins of the Nuclear Thermal-Hydraulics community: regulatory bodies, research institutes, universities and companies devoted to safety analysis. The training dealt with the simulation of thermal hydraulic phenomenology covering both: local phenomena and system behavior, it was subdivided in two parts.

In the first one, we focused on the simulation of a test facility to simulate a particular phenomenon. The participants had to build a model from scratch. The exercise was useful to compare the capabilities of the different system codes in predicting the void fraction in a fuel bundle.

In the second part, a full model of a generic power plant was distributed. Firstly the participants learnt how to adjust the different control systems in order to bring the plant to stable conditions and later they configured an accidental scenario and studied the thermal hydraulic response of the system.

Advanced Thermal-Hydraulic Phenomenology with System Codes. RELAP and TRACE Training (October 2016)

Simulating Thermal-Hydraulic Phenomenology with System Codes. RELAP and TRACE Training (December 2015)

GET Course Extensions and Customized Courses

GET offers the possibility of extending courses for one or more weeks. In such extensions, the participant will have the oportunity to broaden the knowledge acquired in a course under the supervision of dedicated GET instructors.

In addition, GET offers customized courses related to thermal hydraulics, the use of system codes, uncertainty methodology and reactor safety upon request.

Costs will depend on the type of course extension and the number of attendees.

For more information, please contact Professor Reventós (francesc.reventosupc.edu)

NRSHOT (July 2014)

The NRSHOT Seminar will provide a transfer of experience and know-how from recognized experts in the field of System Thermal-Hydraulic Code Calculations including 3D Neutron Kinetics Coupling Techniques. Six different courses consisting of 35 hours each are offered: TRACE beginner and Intermediate, RELAP5 beginner and Intermediate, PARCS-NK coupling and subchannel methods.

RELAP5 And RELAP/SCDAPSIM User and Model Development Training (May 19-June 6, 2014)

The training aims at providing the basic and advanced knowledge to perform simulations for complex systems by using The RELAP/SCDAPSIM thermal hydraulic code of ISS. The workshop will also be a platform of experience transfer in the field of thermal hydraulics