 Nikoleta Marilova, in sem pripravljali točke prezentacije za tukaj, da vidim, če je tukaj. Proste, sem pripravljala tukaj prezentacije vse internationalne energije. Zelo, kako je naša gola, mandat, in izgledanje, na izgledanje. Zelo tukaj, izgledanje, energi in elektriciti for the people who are living in our planet. So you might see that 2.6 billion people rely on biomass, which is considered as renewable energy, but still it's an old source which does not allow this comfortable life and to develop the industry and to improve the sustainable life and development in their countries. 1.3 billion people have no access to the energy at all and while 1 billion people no access to the health carrier due to the energy poverty, because they don't have enough access to the energy and as a result they don't have access to the appropriate health carrier. This is a problem in this world which is separated by nations and rich nations, I say poor nations, developing nations, they should work together to solve this problem if you want to leave this in peace. So what nuclear energy and nuclear power can offer today for the world development of this? Now in 2020, we don't have a later statistics, at least I don't have now, nuclear power reactors generated about 10% of the total electricity generated in the world. I have to say, this is the number is less than used to be few years ago before Fukushima accident, but anyway, this is a huge amount and this is a valuable source and sustainable source of the energy. Now in operation nowadays, or maybe like in last year we had 442 nuclear power reactors in total power about 400 gigawatt electric and they were operated in 30 countries. In now we have 52 new reactors, total power 54 gigawatt electric under construction in 15 countries, it includes also 2 newcomer countries. So still countries have interest in nuclear energy and to production. And let me show quickly the prediction of the nuclear capacity. IA predictions would be done actually in 2014 and 2010, so historically in this plot you can see the, I don't see if mouse is moving here, probably. You can see the dark blue is historical production of the installed capacity of the nuclear power plants which is reaches more or less saturation somewhere in 2010 about 400 gigawatt electric and here you have these predictions done by IA in 2010 and then in 2014 the development of the scenarios for 2020 which we can check now by the way, and also for 2013. You see that in 2010 predictions were much more optimistic for the nuclear energy, so higher than now. But if we look at the let's say pessimistic scenario, we have higher, low and high and low scenarios, so called. If we look at the low scenario and the latest prediction, not latest but prediction 2014, it predicted more or less exactly within plus minus 5% the projection of the electricity now. So of course what I want to say, before and even like 50 years ago we were very optimistic about nuclear energy, how it will develop, that will replace a lot of other sources and will be cheap, reliable and sustainable energy source for production of electricity and other types of non electrical applications for many countries. However, because of several accidents Trima Island, Chernobyl accident, finally Fukushima, we have this public, public does not accept this nuclear energy and we also had to increase safety measures significantly, that increases a lot of the cost of the electricity. So it does make it very competitive with other sources especially with cheap like coal and gas and also with now, it does make it competitive with renewables, that's why we have this delay from those optimistic scenarios to more pessimistic scenarios now. But we should think, if it will be continually like this, if you really want to fight a climate change, this from my personal and not only my opinion, nuclear energy provides real clear choice as a clean and reliable and sustainable, sustainable source of energy for the future generation. So if you look the projections in 2021, it says okay pessimistic, let's say low, we don't say pessimistic, it's low projection, it's the total installed power, capacity of nuclear power plants will remain the same, about 400 gigawatt electric, but if you look it's optimistic, let's say, or high level scenario when nuclear energy will be on demand, we have that in 2050, it will double of the current. But you should also understand, this 400 gigawatt and it's 10% now, if it remains the same 10, 400 gigawatt electric in 2050, it will be only 5% of the total electricity production or energy we say production in the world in 2050. Now let me play one, but I might be video, it doesn't play sound here, interesting moment, maybe I should play and mute this system also. Okay, let me skip this video then because I cannot play from Zoom, I know how to transfer the sound, but it simply shows the main activities in the different fields, which is not only energy production, which we like devoted our today's workshop, but also has different application in different fields in this wide area. You will be able to watch this in the next time. I will send you the link also from the PowerPoint presentation so you can find this information on the web as well. Actually the International Atomic Energy Agency consists of several departments. The main goal is atoms for peace, means for peace and development, means it was created more than 60 years ago, it was idea is to provide to stop developing of nuclear weapons, let's say, to freeze, and instead of that to provide us, the countries, I remember states, with reliable technology for the energy production with nuclear energy, instead of developing weapons, send to develop this, to use this nuclear energy for the peaceful use, for several purposes of peaceful use. Okay, and then we have Department of Nuclear Energy, which I belong to. We have also Department of Nuclear Energy, I will tell a little bit more details about this department later. We have Department of Nuclear Safety and Security, this department is really doing work, how to provide the rules, regulations, and all things which are required, standards which are required for the safe operation of the nuclear facilities and nuclear power plants and all other facilities. We have Department also Nuclear Science and Applications, which is dealing with all, let's say, non-energy production of the use of the nuclear energy such as isotopic productions and also several other scientific applications so like plasma physics for the fusion, for example, for the fusion machines and several other applications, whatever you require, radioactive isotopes or some nuclear reactions, and this is more or less scientific and this application to the agriculture, to the medicine for many other applications. We have a department of safeguards who are many inspectors who control to make sure non-proliferation of the nuclear materials and nuclear, let's say, to make sure that the nuclear energy is used for the peaceful uses and it's that why they call the nuclear, sometimes the energy is called the nuclear watchdog because they control, they inspect the power plants, to make sure that no nuclear materials can be distributed and, you know, hiddenly distributed to the other places. We have a big department of management that manages this huge, huge, very big bureaucratic organization and it requires a lot of management as well. And we have a department of technical cooperation, special department which can accept the money from additional money from the IEM member states, from donors for the specific technical projects developed for others. And I myself, and this workshop is organized by the Nuclear Energy Department, when we have three divisions, division of nuclear power, division of nuclear fuel, cycle, waste technology and division of planning information, oops, excuse me, and knowledge management. So here in this workshop I presented division of nuclear power myself and nuclear fuel, cycle, and waste technology. We will see here the lectures on this topic. In our nuclear power division, I am belong to the section nuclear power technology development, but we also have international project for nuclear reactors section and which is doing with strategic planning how to develop and scenarios of development of the nuclear energy. You will hear the lectures on this also as well this week. Again, and I have a pleasure to lead the fast reactor technology development team which is a part of department of nuclear energy. Again, just to repeat you of the division of nuclear power and nuclear power technology development section. In this section we are... I don't see the slide. Something is wrong, but okay. So in this section we are doing and let's say we don't do the research ourselves, but we are trying to share information, collect information and distribute information about the technologies between the IMF states on different technologies such as including innovative and evolutionary reactors. Evolutionary, I mean this is... we call this pressurized water-cooled reactors, boiling water-cooled... generally all water-cooled reactors including heavy water-cooled reactors, some gas-cooled reactors and also innovative designs such as heavy liquid metal and liquid metal-cooled reactors, sodium and heavy liquid metal both and also gas-cooled fast reactors, molten salt-fast reactors and molten salt reactors in general and also including high temperature... high temperature gas-cooled reactors and if I forgot something supercritical water-gas reactors which are innovative and which are the topic of this workshop this week. OK. So, our activities what we do, as I said, we don't do research in the agency, but we coordinate research, we collect information and distribute it to the member states. What we call this knowledge sharing. It includes the publishing of the documents on the different topics of the nuclear energy, conducting conferences, technical meetings. Technology development, we coordinate research projects, coordinate research projects so-called therapies on the several topics which are chosen by our member state countries as a... who provide experimental data or express the interest in conducting this. We'll explain a little bit later. And capacity building which include training courses, workshops and other documentation including workshop in Trieste in physics and technology of the innovative nuclear power... nuclear energy system is belong to this activity on capacity building. As I said, I personally lead this team on fast reactor technology. It's a small team getting smaller, smaller, by the way. And how do we conduct... And what we define, which activities we should choose to conduct here and what we do. For this, we have technical working group on fast reactor which consists of 20 countries, 20 member states who are interested in fast reactor technology. Plus, we have three observers international organizations. It's OECD, NER, Nuclear Energy Agency and European Commission Joint Research Center and Generation for International Work. We'll talk about this organization later. So, this is group of experts nominated by their governments to participate in this activity. And once a year, we have this meeting of this group when the members report whatever the development in their country. So we know at least what's going on. And also they discuss several proposals which give advice to the IEA which activities to conduct. The same technical working group exists for the other technologies including water reactors, high water reactors, small modular reactors and all others. So you can see that we have this, let's say driving force for our activities by member states due to their representative in the technical working group. There are other mechanisms as well. So this slide shows the main activities of the IEA on fast reactor technology in the 2021, previous and this year. This is what I know very well and I can explain you later in the many, in more details. Again, our main activity is what we conduct and most time and resources consuming it's coordinated research projects but also the several benchmarks and other studies. So we recently completed several CRPs which is so-called Sodium Properties NAPRO CRPs. We also completed PSFR source term CRP PSFR prototype. So maybe I will tell you later about this. Just to give you the idea so we have like two CRPs recently completed. Now we have three ongoing CRPs which I will also discuss. And we have several proposals for new CRPs from the member state that we have to choose which one to conduct. In addition to these coordinated research projects we are also conducting, let's say, more shorter studies. And as a result of those studies we issue the documents on the topics, on the topicals to explain what is the status of these technologies or activities. For example, we conduct in 2021 we completed publishing document on benefits and challenges of fast SMRs. Small, moderate, or medium-sized reactors is also complicated. We will know this story about SMRs later. And on structural materials for heavy liquid metal called reactors. Heavy liquid metal means let and let this matter tactic reactors. We are now just recently conducted technical meeting on development and application of open source modeling and simulation tools for nuclear reactors which is very, very interesting and new initiative I will talk a little bit later. Maybe you as a young forces will be interested. I hope you will be interested in this and can contribute and at least study. And we also recently conducted meeting on state of the art thermohydraulics of fast reactors. And, ok, there are several other activities which I will touch in my presentation later. And one of our important activities several training courses. And here today we have this joint, third joint ICTP IE workshop on physics and technology of innovative nuclear energy systems. Last, not last month actually, last two weeks ago we completed the regional workshop on advances in modeling and simulation of thermohydraulics in liquid metal, fast reactors in India. I'm not sure, you participated? No. This was also, I believe, this regional workshop here is more or less ICTP organized many, many wide, ok, people coming from all parts of this of, let's say, of the world to here. It's very good and very interesting. Ok. And we also conducted webinars. Now, especially after COVID, webinars became very popular and very effective actually. Also, way to breathe and to receive very short and effective easily also without traveling information on the technologies or something. Our main, one of the main activities also is to organize technical meetings and conferences of the IE. And this year we conducted the IE conference on fast reactors and related fuel cycles, which was forced in the series of the IE conference on this topic, which started in Kyoto in 2008, then in France in 2013, in Yekaterinburg in 2017. And effort 22 was originally planned as effort 21 in Beijing, but due to COVID, we have to postpone and make it in Vienna this year. So we had, for this conference, about 365, we have about 700 registered participants and of them 120 participated in person in April of this year. It was the first big in person event in the IE after COVID. Ok. Coordinated research projects like it could be on the different topics proposed by the member states, and actually this is really research which is conducted by our organizations from the member states under coordination of the IE. This usually could be like benchmark specification, sorry, benchmark exercises, when a member state organization provide a specification, usually it's experimental results, promises to provide experimental results on several experimental tests on the nuclear facilities and nuclear reactors. And participants will do simulations based on the input data and then compare this result with experimental data and also versus each other so they can adjust, improve their models and simulation tools, improve their models and also validate the computer tools for the simulation of the reactors. We have several and this is actually very interesting and for me personally also many of them are very interesting to participate as I was did. I will give you one example on coordinated research project on predictive release from the prototype sodium cooled first reactor under severe exit conditions. This was conducted for years usually. Every CRP takes about four years and this was conducted from 2016 to 2020 and this year we published the report. The idea of this CRP maybe I'll show you on the next slide was it's not experimental data of course. It was originally provided by the IGCAR, proposed by IGCAR in India to conduct the research what happens with the sodium cooled first reactor similar to the PF bar prototype first reactor which is now under commission in India if in case of the hypothetical CV accident. We say hypothetical because actually the probability of this kind of accident is very low and it's practically eliminated. What does it say? Practically eliminated. However, practically eliminated means it's physically impossible or very low probability which is kind of discussion on this. But let's say what happens with sodium cooled first reactor is due to the for example sodium if you have the kind of unprotected loss of flow accident you have these pump stops sodium evaporates you have a positive reactivity feedback and finally the core is molten. What happens with this mass of the core molten core if it reacts with the remaining sodium in the pool what happens with this reactor how many potentially radioactive materials will be released to the atmosphere. This is very interesting and very complicated and I think that nobody knows how to because also fortunately we don't have experimental data nobody knows how to answer this question but to try to check between the participants what kind of simulation tools we have what can we simulate and how is simulated and to ensure that at least all these radioactive materials are even released from the reactor will remain in the containment and it's a question and also it's nice and interesting verification or interesting application of the simulation tools used for the reactor here you show in the middle this shows the reactor core hypothetical again and here inside it started from the molten core here and they are huge as you might see here sodium pool and let's say when this fuel molten fuel interactive sodium sodium is immediately evaporated and there is a bubble growing and it grows up and also goes up to the upper plenum when it means huge masses of sodium again and then it collapse condensed back again finally so this is not like simple expansion expansion phase bubble is growing and then make a boom and then it's transient and very complicated three dimensional process which cannot be simulated in two dimensions for example as a result you have the pressure distribution in the upper gas plenum and also distribution of the radioactive isotopes then you can calculate how much of these isotopes and sodium vapor will be released to the containment from the reactor vessel and so on this is so called work package 1 just to show you an example this slide shows another example of the CRP benchmark analysis of FFTF flow-so-flow without scrum test FFTF is fast flux tax facility that was spoken like 30 years ago in 1986 modern city ok in the United States and actually they did really it was not produced in electricity but it's it's it's a big sodium cooled fast reactor with uranium oxide or mox fuel unlike other United States use usually metallic fuel but in this case it was mox fuel or oxide fuel so 400 megawatt thermal but not produced in electricity and it was a loop type plant because there are sodium and loop type reactors which we will maybe discuss later one of the feature this is relatively small reactor core one of the feature of this reactor was maybe I show you here something it's so called gas expansion models which are sub-sub- suba fuel, non fuel, assemblies thigs arranged in the peripheral area of the reactors, eure core is small also in peripheral area and that was at the nominal flow due to the higher pressure of the sodium in inlet of the reactor the level of the sodium in these gas expansion sub-assemblies were high but when the flow is Happ is lower, the level also becomes lower, so it expands, and, gas replaces the sonium. In, in this case, because it's opposite, like standard, because it's the peripheral error, it adds the negative reactivity. And this particular test reactor was working on 50% of power, then the reactor pumps stops, and then, there was the transient process which, okay, the reactor survived this, probably because they da se poželi, da se tudi je sreče začelote, da se poželi, da se začela, da se je izgleda v reaktoru, kjer izgleda vse vočasne. Ko je tudi pravi, paticipati, kaj je tudi 25, jezgleda vse transen in predidit prijevati reaktor vse transenu, First in the blind phase. When we knew only the initial conditions and rector parameters, the own and so on. But we did not know the real experimental data, so called blind phase. The experiment we compared is blind phase. I don't know this is maybe to much. Sreč sem odličen, da se vzelo. Vse CRP odličen je od 4 roče, in FFTF je vzela, da se prišli, da se prišli na drugi roč. In druga CRP je zelo, da je vzela, včajna institutovatomica energi, which is provided experimental data for new turning benchmark of CFR start-up test. CFR is China Experimental Fast Reactor that started in ten years ago in the periods. During the start-up they did several standard tests and provided data for the IA participants. Again, first in blind phase, let's say, when participants didn't know the data and then later in the refining stage when they could compare the data. So here the data were general net criticality when you assemble the reactor core. Then control road works for test temporary reactivity coefficients calculated, sodium void reactivity effect and several other tests which we conducted. This slide shows the timeline of this CRP conducted in four years, which already in November we had the final last research-coordinated meeting of this CRP and I hope will publish next year again. We will publish, for this CRP we will publish actually planning publish not one final report but several documents, which also shows how to use the Monte Carlo Neutronix code for Monte Carlo Neutronix code, such as Serpent II and OpenMC to calculate the Neutronix with Monte Carlo method with example of the CFR of this test. This year we just started a new CRP, which is benchmark of transient from Forza to National Circulation Experiment with heavy liquid metal loop. This is so-called NACHI UP experiment, which is conducted here in Italy, in Brazimone, but nearby, another site of this bay. In Brazimone, it's heavy liquid metal, actually it's led this motor tactic loop. It simulate again loss of flow test. Of course there is no Neutronix, it's simply a simple loop, which includes one mock-up of the fuel assembly, which electrically heated pins and pumps. Then pumps stops and you have a transient, which goes through the fourth conversion. Finally you have established a National Circulation mode, which is also obviously this test section, at least not necessary reactor survives, in which you have about 10% of the power, sorry, 10% of the flow rate, of 10% of the nominal flow rate, conducting, which is enough to cool this test section. And it also provides, let's say, it doesn't copy the reactor data. It provides the materials and experiments for validation of the computer codes, which are used in the world for the simulations, such kind of experiment. And this is our first therapy related to heavy liquid metal, because now let cooled fast reactors become also popular. We also conducted recently technical meetings on state of the art of throm hydraulics of fast reactors, which included many, it was a review after maybe 20 years, what is the new development in this, what is again, what is kind of new experiments, and also reviewing the state of the art of this technology, modeling and simulation experimental results for the throm hydraulics of fast reactor cooled by. Actually it was mostly related to the liquid metal, sodium and lead, but also several gas and several contributions were related to the gas cooled reactors and molten soil cooled reactors. Okay, another interesting thing, actually, which I was personally, was very interested in the, it was a technical meeting on development and application of the open source modeling and simulation tools for nuclear reactors. So called on core initiative, which we started in the year with help of several, also lecturers will be explained probably this week on this. Actually, the idea is usually it was in-house code or proprietary codes for to simulate the nuclear reactor such as, for example, MCNP, also every commercial CFD codes, but the new trend also started. Can we use the open source approach, open source tools for the simulation of nuclear reactor? And that was discussed on this meeting. The benefits are obvious because it's freely accessible and also easily accessible. So all students, professors, especially for educational purposes, you can quickly access the code, you can run the code, you don't need to apply especially for the light sensing and so on. You just use and also this code itself or developers of this code benefit from this because you have more users, they users contribute to development of this code for the testing and development of this code, so it becomes popular. And one good example is OpenMC, which is Monte Carlo simulation code for the, okay, for the Neutronics and the reactors. Another example is OpenForm, GenForm. There are several branches of the OpenForm. OpenForm is a CFD code for the simulation of everything. It's just general CFD, but there are several branches which use this kind of CFD codes, open source code for the simulation also of the nuclear reactors. And I'm inviting us, you, also myself, to revisit these pages and to see how can we use this in future. We also work closely with the IED department of Nuclear Safety and also with GIF generation for international forum and we conduct in every year workshops on safety of the liquid metal code fast rattles. Started in 2010. Every year we have an exchange of information on this on the LMFR safety. It used to be safety of the sodium cool fast reactors. Now it's more general, includes heavy liquid metal and safety of LMFRs. Okay, one of our important activities is joint ICTP IE workshops on innovative nuclear systems. That's very good, like ICTP invited us to conduct this workshop here because they have many connections and experience to propose to, let's say, to select the participants from around the world, from all countries and collect here in this beautiful place and to organize these workshops. I would like to thank this ICTP for this opportunity again presenting and now it looks also better. So maybe for the group photo we can make it. Unfortunately today I am the only in person from all lecturers, all others are participating online so I suggest we can do it on Wednesday if weather is good or any other days for the group photo but we also should make group photo with online participants as well. Okay, we have several simulation tools also which are supported by the agency in this in our section. One of them is Sodium Properties Calculator just recently released. It's NAPRA so called. You can search for NAPRA Sodium Properties Calculator and find. It's in addition to our big public to the CRP and publication of the properties of the sodium which once you can use also in textual form but you also can check and see what are references for the sodium for the different ones. Another educational tool it's educational part of the hour. We have a suite of the educational simulators for the nuclear power plants and in this case which also I was doing and involved in the activities on educational simulator of the sodium cooled fast reactor which is already obtained by the IEA, by the vendor and now we are preparing the technical documentation and exercises manual which can be used for the student but if you are interested you can already now request the simulator and we can distribute it for you for the purposes of the testing and also for the education. Here this slide shows our main activities in 2020 which was international conference on fast reactors with a few cycles enabled several other meetings and other events and this year we conclude this joint ICTP IE workshop on physics and technology of innovativeness here in Trieste. I finally would like to advertise that the IEA is hiring the personnel and to work in the IEA is fun I would like to you can search how to find the employment just search this employment in the IEA and I invite also young generation to join the agency if you have interest and to spend several years in Vienna working in support of this nuclear energy in atoms of peace in general. Okay, thank you. Before, thank you for your attention I also would like to show briefly the workshop program and introduce our lecturers also. So we will have this, I think you have this program already there the idea is like in the morning and afternoon we will have the big lectures from our professors and other experts around the world and in the afternoon, in the evening we will concentrate on the group activities means we will be providing you several simple exercises which we will do in groups and first of all please like in the end of this day let us or we can also do randomly for you if you like or you can also compact in the several groups try to make it like a mix for the gender, for the geographical distribution not to be randomly distributed I would say. We have by the way very nice gender representative here I know like 50-50 from my, you know, I don't count this is good because we are welcome we are welcome very much female in my age you know, already unfortunately we have very few female let's say expert because we started like it used to be when I started my education in 40 years, I forgot already it was like a job for the man and but now and that's why we have this too many let's say female underrepresented in nuclear engineering in general obviously because you start from if you start from 90% or 95% of men you cannot expect to be 50 women to be representative after these but now during because now fortunately nuclear engineering becomes popular also through them women and we have special initiatives for this and the IE International Atomic Energy agency supports this for example, we have a scholarship for Maria Skolovska-Skuri's scholarship so those who are working now in the master course can apply for this if you need more information you can just ask me directly if you are in the master course the first or second year of the master course you can apply for this scholarship and obtain this scholarship this is for the female participants okay again, the idea is we will give you several activities and you can do these exercises in the evenings especially like now it's no sun no swim possibilities so then you can concentrate on conducting these exercises and the last day on Friday we will discuss it every evening what's going on so you can ask questions and we just consult we will be applying actually three activities I'm not sure we'll see how it goes but you will be informed so in the last day I believe we can do three or four groups also depends on you as many and the last day we will be all three groups will be delivered short presentations on the results what happens we will see compare the results because it's too short and also we understand that you are also walking here all the days and in the evening it's maybe not enough but just to present this exercise which will be followed by these group presentations and then we will I think Nikola will distribute the certificates for the participation in this event tomorrow and on Wednesday in the evening we will have poster sessions you all, thank you very much you all prepared the posters which can be distributed there and we will discuss this poster we will have like two hours poster session every evening and we will select maybe one or two or three posters as the best posters I know that because we want to distribute as many awards as possible here then please be prepared to ask the questions the lectures will come and ask you the questions we will have a discussion and please try to present your poster as much as possible to deserve this one of these awards and maybe all if you have questions about the program let me know ok, we can do please also during at least my presentation please interrupt me also participants from the online participants please interrupt me and send the question whenever you have chat put in chat or raise your hands online or interrupt me anytime from here now let me, I have a pleasure to present our lectures that will go as they not as of the importance but also as they appear in the program and one of them is Cheray Obatra who is chief technology officer in terapraxis and lead catalyst he just started this job in this summer before that he was a nuclear engineer and project officer here in Zajen in fast reactors team and also in small model reactors team since 2015-2022 and he has two master degrees in nuclear engineering and another in nuclear reactor physics and I believe that Cheribatra is now online with us Cherayo would like to add something maybe you can welcome participants also Cherayo, can you hear us? ok disappeared somewhere anyway, you will see him soon he was actually supposed to be of here in person but now today he will be also presenting online another lecturer which will be starting this afternoon presentations is professor Kassilov he is the managing director of the regional network for educational and training in nuclear technology star net project he is also professor of national research nuclear university MIFI in Russian Federation he has PhD in nuclear engineering and he is experience is nuclear engineering education, training nuclear management, research and development in nuclear technology international cooperation he is more than 50 years has experience in the nuclear field and he used to work in the IA nuclear power division and received in 2001 he received American nuclear safety training excellence award and also published about 150 scientific publications during his research career which is he still continue professor Akira Tokuhira sensei from from Canada Ontario Tech University he will be also presenting this afternoon like he will be presenting online and since Canada time difference they all in North American lectures will be presenting in the afternoon in the evening he was the dean of students in this Ontario Tech University he has great very long experience of his working in his working list appointed in very like several United States Organization Aragon National Lab Adako National Lab Pacific North National Lab thank you for noticing and he works actually in several several appointments he was also born in Tokyo, educated in the years he got his PhD in nuclear engineering from Purdue University and he worked also in JNC, I don't see, I met him first when he worked in JNC now JEE in Japan ok, Akira will explain him he is also a member of women in nuclear of Canada by the way, so he supports effectively women contribution to the nuclear engineering ok, so for tomorrow we will have online lecture from professor Vladimir Artisiu who is now since two years, more than two years already is a consular and advisor to the director general of state atomic energy corporation Rosatom in Russia he is also contributing since 2016 he is a member of state advisory group for nuclear energy into the IE Vladimir got his PhD from Oblin Institute for nuclear engineering in 1991 and doctor engineer from Tokyo Institute of technology in 1997 so he is classmate for our ladies representative here from Oblin and also from TokoDial the same and in nuclear engineering and fuel cycle development in Tokyo Institute of technology and INP professor Adrian Bugges is his professor of engineering physics at McMaster University in Canada and his specialty is nuclear reactor core physics of different designs particular Kando reactors heavy water reactor Kando in Canada and several different other reactors including the future designs and especially we inviting him as expert in super critical water reactor and molten soil reactors which are innovative reactors and topic of this workshop prior to beginning professor at McMaster Adrian was the manager of the reactor core design in the ACR-1 congrid at atomic energy of Canada and before coming to Canada he was professor of experimental particle physics at McMaster University participating in scientific experiment in lab and design of experiments at large carbon collider and he is a fellow and past president of Canadian Nuclear Society he already delivered lectures two years ago sorry, four years ago here in Trieste and that very well received here another representative of the he is Alexander Bishkov from the IA he is senior nuclear engineering expert and he is working in the in-pro section of the IAEA our sister section he before rejoining IAEA two years ago he is a genetic post of Rosatom representative to the international organizations in Vienna from 2011 to 2015 he was served as a deputy director general of the IAEA and head of the department of nuclear energy Alexander will deliver several lectures and very interesting lectures I believe he will be arriving tomorrow and he was graduated from Moscow State University in chemistry in 1982 and he covered a lot of the areas and he spent devoted his life to the nuclear engineering and he was also published and he was a co-author of about 100 scientific publications Professor Takashi Takata he will be again arriving tomorrow and starting his lecture on Wednesday and since 2021 he is professor in department of nuclear engineering and management of the University of Tokyo and he is the chair also of the risk assessment technical committee of the standard committee in atomic energy society of Japan and visit researcher in Japan atomic energy agency so he is doing a lot of work in this field and we will see in his lectures his two lectures probably three lectures on the topic this week he received his PhD from Moscow University in 2004 ok Kristian Lege Dr. Kristian Lege from CIA former work at the CIA now retired but consultant in the CIA he will be again arriving tomorrow and deliver several lectures on the several topics and as ok after retirement he is consultant and scientific advisor for CIA in Kaderaz Kristian supports in both his text also ok and he actually has very exciting and long experience in nuclear engineering technology and since 1979 after he received completed and received PhD from Institute of National Polytechnica de Toulouse in France he was doing with many in especially on the sodium cooled fast reactors and his topic is the sodium cooled fast reactors and I would like to add to this introduction that Kristian participated in previous two workshops here in Trieste and this will be his third workshop in Trieste again finally I would like to introduce Nikoleta Marilova who is supposed to be here and she was not able to attend and his second year is nuclear engineer in fast reactor technology development team working with me and he also has short but very intensive experience in nuclear engineering since 2016 when he got PhD from Kastro Institute in Technology KT in natural sciences in 2022 and before that he completed master science degree from Ecole Polytechnique fédérale de lasagne EPFL what we saw and also in Pao Sredl Institute PSI in nuclear engineering finally myself I told you already that I have a pleasure to work as a team leader of fast reactor technology development team in the AAM I also received the PhD from Oblask Institute of Nuclear Engineering in 1994 it's from so we remain also after engineering from Tokyo of technology so also with you and I worked in IPP in Oblask in TTH Tokyo Technology in Japan JNC which is JEN now I am PE in Oblask and KIT in Germany form FZK and I am happy to see to welcome all of you here today and this week in this great workshop I just before we go I just want to ask if Nikoleta Nikoleta, are you with us? Hello, can you hear me? Yes, we can hear, so welcome How do you feel Nikoleta? I hope you are better So we can join you Thank you very much, I am very excited for this workshop Please... Sorry, I cannot be there We miss you. Please add few welcome words to our participants So very excited for this workshop for the lectures in the next days and I hope you will all learn as much as you also have expected and Yes, so I hope I wish you all a great few days Ok, great, thank you and then Any questions? Oh, this is perfectly in time Any questions to me on this workshop in general on the program Ok If not we will have a coffee break and I know if you need a group photo we can make a group photo also today Also, please, those who are online please come at 10.45 here in Italy Central European time means in 15 minutes and we make a group photo online also as well Ok, thank you