 Then we continue. So I will present to you our activities at the IAA on computational tools for nuclear reactor analysis. And also I would like to welcome you to this workshop. All of you here and also our large online audience. So as you already seen this slide, so I will just skim through it, that technology development, we're looking at the knowledge sharing technology development and capacity building. And here is a good overview of our activities in a fast reactor technology development team in the year 2022 and 2023. And the ones that you can see in red are in a way related to the computational tools and simulation tools for reactor analysis. So we had a very great technical meeting on development and application of open source modeling and simulation tools for nuclear reactors last year in June. We had a very large international conference on fast reactor and related fuel cycles where many authors submitted papers and presented papers where they use open source tools. We are currently developing a basic principle simulator for sodium fast-code reactors. And we also had a variety of training courses and workshops such as webinar series on multi-physics modeling of nuclear reactors using open foam. And of course this great workshop this week. I will talk a little bit more in detail about this just in a minute. But I would like to introduce you to ONCOR initiative because this workshop really is within the framework of this initiative. So ONCOR stands for open source nuclear codes for reactor analysis and it is an initiative. It's an IAA facilitated international collaboration framework with the aim to develop the applications of open source software in order to support research education and training in a field of nuclear science and engineering which encompasses also fusion and fusion. We invite institutions and individuals to participate in this initiative and to collaborate and benefit from this development of open source software in the field of nuclear science and technology. The objective of this initiative is to build and preserve knowledge in the field of open source software and open access data and to facilitate this exchange of information within our community for nuclear science and technology. Also to conduct a survey of all the existing open source software, open data and to aid make these accessible. To identify the best practices for the open source software development, verification and validation. To access the features, gaps and opportunities for integration of already developed and available open source software and to facilitate the sharing of all this about the reference solution, the benchmark problems, the data. To organize various education and training activities and to promote the variety of these individual tools, also for education and research environments. And of course we promote this initiative and we broaden the engagement among the IAA member states. We would like to have more and more of the IAA member states engaged in this initiative and who is helping us in this on core initiative is our on core expert group of which many members are here today with us as lecturers. They help us to identify new activities and benchmarks and give us the good overview of the available open source software and data and promotes these worldwide. So here is the IAA website on on core and if you click on members area, you will get to this side where you can find the description and also the list of codes. And this list of codes is a really great summary of all the open source codes available for variety such as for neutronics, thermohydrolics, processing, et cetera. If you're interested in high temperature gas or reactor code package, this is under the IAA. So if you would like to have access then you can just fill out this form and we will give you access to this package. So as I mentioned, this platform, we have over 35 open source tools covering really a variety and these two tools hosted and distributed by on core such as VSOP and Stacey. So please do not hesitate to have a look at this page, have a look at the codes. If you're interested and reach out, you can also, if you're developing your own code, open source code, you can also reach out to us if you would like to have this shared on the platform and we can evaluate its completion and then share this as well. As Vladimir already mentioned, this on core initiative, so the IAA was designated the EPFL in Switzerland as the collaborating center in order to support the member states in increasing their modeling and simulation capabilities in a field of advanced reactors. Carlo was the focal point for this collaborating center until last year and now Alessandro took over. I will just give you also a brief overview of the major past events related to this on core initiative. As I mentioned last year, we had a technical meeting and also last year, August to October, we had a really great webinar series on multi physics modeling of reactor analysis using open form and this year we have this workshop. So this technical meeting, the objective was to share and discuss recent developments in the area of multi physics modeling and simulation using the open source software and open access data. And as goes for the on core initiative, this was to support research and development, education and training in the community of nuclear science and technology. This technical meeting involve also various live workshops on several tools. Open MC we already had, we had open form, so basically like this week but we also have Moos and Army. So participants presented their work, their papers and then we have collected basically what was presented in this meeting ranging from motivation, experiences, challenges, best practices, advanced applications and really a good overview of all these open source tools and with the aid of these experts who are involved in a technical meeting, we're putting together a technical report series publication which will be open to all, publicly available and we expect to release this in 2024. So maybe in Q4 2023, sorry, and you may see an email from us because promoting this technical report series. Here is just a brief overview of sort of what was discussed during this technical meeting. We have touched upon the motivations and challenges of open source software such as from the user perspective, from the developer perspective, various challenges such as switching from an established commercial call to the new open source, what is the time investment, how to do the quality assurance if you have a single group developer, how do you, if you have really reliance on this single group or a single expert, how to do the best practices, what would be the advice of the experts such as use the version control, use of automated continuous integration for quality assurance, really making sure the documentation is up to date that there are tutorials and startups to encourage the audience to use these codes. And also of course, the role of open source software in education and training and how to invite more people to use these open source codes to provide this adequate training in the use of various softwares to help grow the number of skilled users. And here we already do that by webinars, workshops, tutorials and online courses. Which brings me to the webinar series of on multi-physics modeling of nuclear reactors using OpenFoam. So OpenFoam will be introduced very briefly so I will not go into detail but just to let you know that this webinar series really provided the audience with up to date information about the possibilities provided by OpenFoam and also the family of codes based for OpenFoam and the strengths and challenges, practical guidelines. But it's also more of like a general introduction for your own further learning. And it is where 12 lectures over the course of six weeks which covered the basis of OpenFoam, the problem definition, geometry and mesh generation, source code and then various tools. Some of them will be also covered this week such as containment foam, gen foam, off-beat and gen ROM. And I would like to invite you because these recordings of all these lectures, the slides are all available unto this link. They will be available for still a long time and also there were a few lectures on hands-on exercise. So the lectures were showing how to approach the problems. So it's not just lectures but also some hands-on exercises. As you know, this workshop, this week is our third big event in an OpenCore initiative. And as Vladimir already mentioned, we will cover gen foam, off-beat containment foam, these codes related to OpenFoam and also of course OpenMC, Army and OpenFoam for Fusion. One of the outputs related also to OnCore is Neutronic Benchmark of CFR Startup Test Training Core Series which will be available also this year. And this training con series is a great on-correlated output from this coordinated research project because it shows how to perform Monte Carlo simulations with two tools, Serpent and OpenMC. And it's really a very comprehensive and detailed training core series on how to approach modeling of the core of the fast reactor. It is intended for students, also early career engineers. You don't have to have a very high knowledge of computational tools and simulations but it's really very much in detail. I will just give you a sneak peek here. As you can see, so you have the CFR core and then how to really discretize up to the pins, how to model that, how to really prepare your data, how to do it for deterministic versus Monte Carlo tools and how to really make the OpenMC input in the same way, how to do the Serpent input. And then you will have here the real experimental data from the CFR reactor and with the two tools which is really what results do you get and the comparison. So this is just for one example but there are three. This was developed with the expert, one of them is Jivon here. So she will also probably show you, this will be related to the CFR core modeling that we will do on Tuesday. Lastly, I would just like to also promote our Sodium Properties Calculator. This was developed after we had a coordinated research project on Sodium Properties is a very comprehensive literature review of all the properties ever published on Sodium and this was then put here online and you can look at various properties and calculate several properties. So all these references are put here. This is also open to all. This is also widely accessible. So this is something of interest to you. Please do not hesitate. This is online. Lastly, our Educational Simulator for Sodium Cold Fast Reactor. This was developed in the past years. It's a very real simulator. It's for education and training. We would like to distribute this year. We are just finalizing the exercise manual but this is also something of interest to you. Please do not hesitate to email us. We can distribute. Thank you very much. This was the overview for the Oncronitiative under which this course, this workshop is this week. And with that, I will pass the word to our expert to teach you guys on open form.