 Good afternoon, everyone. I'm Takashi Takata from the University of Tokyo, Japan. And I really have to appreciate all the staff of this workshop to give me an opportunity to have the lectures. Thank you. And today's my topic is development status of sodium cooled first reactor, especially. I would like to focus on the Japanese situation. And however, I think that it maybe has a good chance to discuss what kind or how we use innovative nuclear systems is through this presentation. Yes, this is today's my contents. Maybe I have 14 minutes, something like that. 45. 45, okay. And those are today's contents. And before starting my presentation, I sincerely appreciate the staffs in the Japan Technology Agency, J&A, to prepare the many materials of this presentation. And today, firstly, let me briefly introduce that why is that the first reactor and already in the last lecture, we, sodium cooled first reactor, advantage of the sodium cooled first reactor is already open. But anyway, I would like to talk about the words of the first reactor and significant currencies of the first reactor cycle technology development. And then I would like to briefly introduce that current status of the first reactor development in major countries. Maybe from the French, he was much more aware than me. And then I would like to show that the first reactor development environment in Japan, especially from the viewpoint of the governing decision. And this is a typical schematic of the first reactors. And one of the great advantage of the first reactor is the bleeding, as shown in here. If we use that first neutral spectra, uranium 238 can be changed to the plutonium. And this plutonium, we can use that as a fuel, which is same with the uranium 235 or something like that. And the right view graph is typical first reactor types in generation four. And maybe this afternoon, we will have another excellent lecture for the generation four. And I would like to skip the most detail of them. And as in last lecture, sodium has a much great advantage. So in Japan, currently, we are focusing on sodium first reactors. In addition to the last lectures, I would like to mention about the one advantage of the liquid sodium, especially in Japan. That is the density. The sodium density of the sodium is lower than that of the water. And from the viewpoint of the throssing of the reactors due to the seismic issues, the sodium has a greater advantage rather than, for instance, that this mass of red. That is also very important key technologies. And I think that many of you know about the why is the significance of the first reactor cycle technologies. And this blue line is a famous statement by Andy Coferini. And here, I would like to show that why is the significance of the first reactor cycle technologies. And of course, in the right order technologies, we have the green house gas emission and sustainable for load following operation. Load following operation, I would like to explain later. But first three items is especially very important in terms of the significance. First one is the efficient breathing. And this can make a sustainable domestic energy supply, especially that in Japan, Japan has almost no energy resources. And we have to take into account that what kind of the sustainability have been achieved, especially in terms of the energy. And the second one is not the electricity, but still due to the characteristic of the first reactor, that means that we get high temperature systems. So use of the high heat is also is one kind of the significance. And the last one is radioactive decay function using the first user. And this also, this is already lectured in today's first lecture. But anyway, those kind of the deduction of environmental burden is quite important from the viewpoint of the sustainable energies. And let me briefly each terms. And the first efficient breathing, this view graph shows that total electricity, total use of the energy comparing with the coral, petroleum, nuclear, linear or something like that. And if we had some peak out of fossil fuel using, we have the gaps here. So to solve this gap, we need, at least in Japan, we need this kind of the first reactor cycles. And the first reactor cycles coupled with MOX, right-water reactor cycle system. And to do that, we can fulfill those gaps. And also, if one take into account those kinds of the first reactor systems, so breathing can be ideally, it will prolong to the resources of the uranium. As everyone knows that uranium 235 is only less than 1% of the total uranium. And if ideally, ideally, we can make that breathing from the uranium 235 to the plutonium. It almost, it's just a numerical, no, not so numerical, it's just a calculation. But if we have only that 100 years resources, for instance, then it become to more than 3,000 years. Of course, it's an idea. And the actual case is approximately 1,000 to less than 1,000. But still, we have much more resources. So that is a very important significance from the viewpoint of using that first reactor. And the second one is the use of high heat. Maybe we need to discuss about that. I think that one of the key point in innovative reactor is the variety types of the reactor. That is a key point, I think. And from the viewpoint of the generation of the electricity, especially in Japan, we need a lot of the electricity. But at that moment, maybe it would be better to focus on the small reactor, small modular reactor, but also the large type of. But that situation changes from the countries. And from the viewpoint of the energy, of course, electricity is one of the most important part. But from the viewpoint of the transportation and another industrial resources, it would be better to think about not only the electricity, but also what kind of usage can be applied in innovative nuclear reactor. And for instance, if we use that high heat, maybe we can make, for instance, a hydrogen production and desalination and some kind of direct use of the industrial process. And sometimes it may depend on the situation in the country, but in Japan, sometimes we take into account some kind of the heat storage by using that high heat. At that moment, I think that we do not need much more large type of reactor. Maybe that some number of the small type reactor is suitable for that. And next is radioactive decay function using that first neutron. And as mentioned that, as mentioned before, that first reactor uses on the recycle, the minor actinide fuel achieving a closed cycle. And to do that, we can make that reduction of the total radioactive waste, almost at the one-tenth or something like that. Of course, one of the other candidate is accelerator-driven systems, ADS. And maybe we need some discussion, but from the viewpoint of the plutonium reduction, maybe ADS has not so good advantage. At the moment, of course, in the first reactor, one of the key point is how to make the fuels, including the minor actinide. That also be a kind of the key technology to fabrication of the fuel in case of the radioactive decay function. And also that here, the right side view graph shows that the potential toxicity from the high-level radioactive waste for the generated energies. And maybe similar bibliographies are already shown in previous lectures. But anyway, if we make that those kind of the radioactive decay function by using the first reactor, we can reduce not only the total amount, but also the total magnitude of the toxicity can be achieved. That is another thing. And let me move to the current status of the first reactor development. And for instance, as in the last lectures, unfortunately, currently, after the project was postponed, right, unfortunately. But they still have the many experience of the super-phoenix plant during the construction and its operation. And also they still have the many anti-activity, such as the simulation technology. And laterally, I would like to briefly explain about the international collaboration between the French and Japan. And in the United States, they have the operation experience of the experimental reactor, EDR2 or Fermi reactors. And related to anti-activity are ongoing to maintain, keep their technology levels. But in the United States, they have several plans to construct the new first reactor. One is the birth-style research reactor. This is just a reactor for irradiation or something like that. And this is already planned to start and it maybe start in around 2006 or something like that in operation. And Natrium. Natrium is the name of the sodium reactor by a terra-flower. And this is also planned to start in around the later of the 2020. And in Korea, President Yoo, who took the office in May of this year, advocates nuclear power generation, Recursion Center promotes the small modular reactor development and the nuclear power generation export. And the construction of the prototype reactor, EGSFR, will be resumed to middle of 2020. And in Russia, Russia is one of the most advanced countries in using that sodium-cured power reactor. And they already had the experience of the operation of the prototype BN600 and the demonstration type of the BN800. And now they are planning to develop BN1200. But here I just say that maybe it in 2030s or something like that, but I'm not sure in the current situation. And also, from the viewpoint of the irradiation test reactor, MBIR is planned to operate around the rate of the 2020. And for instance, from the viewpoint of the first spectrum, test reactor, irradiation test reactor, we do not have many reactor current. For instance, in Japan, Joyo is still under the re-licensing process and we do not make that any experiment. And that is one motivation to prepare that the versatile test reactor in the United States. And in Russia, maybe we mentioned some, if I mistake, if I made a mistake, please correct it. Maybe that they apply that the MBIR, replace of the DOR, MBIR. MBIR will replace BOR6. BOR6, yeah, right. And for India, the test experimental reactor with the first generation FBTR has been operated since 1985. And the prototype BFB is under construction. And demonstration and the commercial reactor of CFBR will be deployed in later of the 2020. And in China, they are just skipped of the experimental reactor by importing from the Russian technique. But still they have the plan of developing that demonstration reactor CFR600 in 2020s. And briefly discuss about the detail of the major countries. And in general, France and the United States have achieved the nuclear fuel breeding technology itself. And their main, currently their main target, I think that the new management, radioactive waste reduction and multi-purpose use of the first reactor. And as I mentioned that in the French, unfortunately that the Astrid project is postponed. But still they have the plan to develop the commercial first reactor later on this century, right? Maybe earlier, okay. And in the United States, they are now planning to construct the first type test reactor and natural reactor. And for instance, in Russia, they already have the higher breeding ratio for energy securities. And they are now in operation of the BN800, maybe the commercial reactor of the BN1200. It's planned to construct it in 2030s. And India also has active first reactor plan. India and China also has active reactor plan. And let me move to the Japanese histories. In Japan, we have the two first, two of them include first reactor of the experimental reactor, Joyo and the prototype reactor, Monji. And this is a brief histogram of the Japanese first reactor development. And in 1977, Joyo reached the first criticality and Monji first criticality is 1994 or something like that. And unfortunately, there was one incident of the sodium fire in Monji and it stopped more than 10 years. And just after stopping from the sodium fire incident, unfortunately, we had another incident of the drop in the equipment. And during the stop of the Monji, we had the East Japan Great earthquake from the 2021. And after that, Monji was decided to stop its operation and move to the decommission. And Joyo is still, we will try to re-license it. I will later discuss about that. And after the East Japan Great earthquake and we had accident in Fukushima nuclear power, Fukushima Daiichi nuclear power plant of Teppuko. But still, we need, in general, Japan has a lack of the energy sources. So we still continue to keep the kind of development of the nuclear on the instance of the fifth strategy energy. This is the government decision. And also the issues of the first reactor development policy. I will explain that later. And after that, as you know that currently, we have some kind of small regressions of the nuclear technologies due to the green gas-house effect. And also in Japan, we also have that green growth strategies to the, to our, to the 2050. And on this year, strategic energy plan is updated from the fifth to the sixth. This is a brief explanation of the Joyo experimental reactor and mission of Joyo and its major achievement listed here. And the mission is to demonstrate that the basic function of the first leader reactor. And I do not mention about that. Joyo itself has no electricity generation system. It's just an experimental reactor. And the other mission is to perform the irradiation experiment on the elements such as the nuclear fuel and materials. Those irradiation experiment is quite important to establish the innovative reactor, especially from the viewpoint of the first neutron spectrum. And the last one is to verify the innovative technology for the future first reactors. And Joyo showed us a good demonstration about that, those mission. But it also that, unfortunately, we have one accident of the gripping and the droppings of the piece of the element. And during the stop, it also happened that East Japan earthquake accident. But let me move that to current status law of Joyo. And JIA already submit a Japan to make energy agency submitted its application for the Joyo to start to the Nuclear Regulation Authority in Japan in a way. And many of issues go proceeded. And we hope that maybe not so future, I mean that maybe that two years or three years later, I hope it works again. It operated again. And beyond the design basis accident and the first accident measure are currently under review by NRA. And also JIA is currently required to inform the local government authorities of to establish the basic plan for the spent fuel management before restart of the Joyo. But anyway, now that from the viewpoint of the operation of the experimental reactor, Joyo goes, of course it's a little bit slowly but it goes for. And this is a prototype first reactor, Monji. And also the missions and the major achievement are listed here. And the main mission of the prototype reactor is to demonstrate the reliable power generation performance. And another one is to establish the sodium handling techniques. And for instance, in Russia, they have a lot of the experience of the handling technique of the native sodium. And if once we lost those kind of techniques, it is quite difficult to go back and to resume on their last position. In that sense, we need those kind of the handling technique is also being of importance. And here, we just listed the major achievement and Monji established that first reactor product design and accumulated operation and maintenance experience. It includes some kind of the data using the peer-based probabilistic risk assessment. And of course, it not went well but still we will have the experience to make that generation, power generation. And it also that the bleeding capacity approximately around 1.2 is achieved in Monji. And this is a summary of history and the current status of Monji. And as I mentioned that in 1995, sodium leak accident or incident has happened. And we stopped more than 10 years. And just after preparing the re-operation, they have some drop accident. And during that, we have the great East Japan earthquake and governing that immediately, not immediately, governing just changes their decision from keep operating to finish its operating. And in 2013, there was some, not the incident but there are some kind of the security, not the security issue, but there's a kind of the maintenance issues. And after that, in 2016, decision was made from the Japanese government. And from 2017, Monji is preparing for the decommission. And currently, I just mentioned about that here. Okay, in 2020, on this year, transport of all fuels from the reactor base cell to the EVST is finished. And then, currently, we have no fuels in the reactor core. We then, we proceed that the next approval, application, approval of the application to the NRA. And maybe, I think that the JEE discusses with the liquid sodium with French government. Maybe, I think that most of the liquid sodium used in Monji will move to the French and, no? Okay, and then, so there was the UK to store the sodium to get it machined? I see, yeah. And unfortunately, it also was a fact that maybe 10 years ago in Japan, we also had one specific company, private company to produce the liquid sodium for the first reactor, but it was gave up to keep the situation. And currently, in Japan, we have no such a kind of production of the liquid sodium. It goes, yeah. Yeah. Yeah. They stopped, yeah. But that's a fact that Japan, in Japan, we have still got a very, not easy situation to keep. Okay, let me move the first reactor development environment in Japan. Before that, I would like to mention that how energy resources in Japan that Japan has left or that have any, and you will see that from the viewpoint of the 15th, we will have that 20%, around the 20% of the nuclear power plant from the viewpoint of the electric generation. But unfortunately, as you know that maybe, last 20 years, we have only, okay, oh, so. And we have only several new nuclear power plants. So that means that in general, in Japan, from the licensing, we applied that 40 years operation. And if we finished 40 years, maybe we will have the lack of many nuclear power plants and it does not satisfy the 20% of the 20% at the end of 2030 or 2050. And from this viewpoint, existing nuclear power plant, we will have another issues for extending of the operating back plant. And of course, we need to make some kind of new building, new construction of the next generation of nuclear power plant to keep that goal. And for instance, in Japan, we have the main three items, promotion of the R&D in terms of the nuclear power plant and why is that advanced development of the first reactor. And the second one is demonstrates a small modular reactor technology. And the last one is that develops the basic technology of hydrogen production. For instance, using that high-temperature gas reactor. But last two, it's not mainly comes from the electricity supply, but it's just coming from keeping the technology. And from the viewpoint of the first reactors, R&D, that is managed by a strategic roadmap issued in government. And this is a development policy. And maybe I would like to skip this one. And that is a strategic roadmap for the first reactor development. And from the viewpoint of the significance of the first reactor cycle development, we have to take into account the efficient use of the natural resources and the becoming the energy independent companies. And to achieve the sustainable radioactive waste management, we have to take care that amount and the electricity must be reduced. And from the viewpoint of the target reactor technology, we still focusing on the sodium-cooled reactor with the MOX fuel. And of course, another candidate is the metal fuel. And later in, maybe I do not have a lot of time. Maybe I'll later discuss or explain about that. In Japan, typically we have developing to the loop type, sodium-cooled first reactor. But currently, from the viewpoint of the knowledge from the another companies, we take into account the both loop type and the fuel type. And there is a schedule and the last one is sharing the role of the development systems. And in Japan, Japan to the energy agency is mainly as a contribution to the development of the first sodium-cooled first reactor. And they still keep their position to provide that research infrastructure to develop the first reactor in Japan. Okay, this is an outline of the R&D in Japan Atomic Energy Agency, they're here. And okay, I will speak to the detail about that. And mainly I do not explain the detail about that, but from, we are now here. And first five years, we just check the competition of the development phase. And then we will have the next 10 years to design phases. And currently, we are planning to basic design construction start to 2030 or something like that. And as I mentioned that currently, it is not easy to make only closed development strategy in one country. And we need international collaboration to make a efficient development. And from the viewpoint of the first reactor, we also have that many contribution, collaborating works. For instance, French and Japan. And the other one is the United States and Japan. And of course, we have some collaboration with that GIF and IAEA. And from the viewpoint of the standard, we also have some connection with that ASME and JSEME to establish that standard. And this is an example of the advanced loop type one. And the loop type means that here we have that intermediate heat exchanger separately allocated to the reactor vessel. This is mainly comes from to make that compact reactor vessel for seismic issue. But from the collaboration with the French people, and we also now take into account that another type of the full type reactors. But in that case, you will see here from the countermeasure for the seismic issues, we take into account some kind of the mechanical isolation systems. And this is a requirement from nuclear innovation from the Japanese government. And mainly we have that three issues of stable power supply and the natural resource recycling and flexibility. And from the viewpoint of the further improvement of safety, maybe I would like to skip, but we have that some equipment to reduce that severe accident or co-disruptive accident to using that, for instance, SSS or radar systems. If you are interested in, I will later explain about the why the system. And this is some kind of the example of stable power supplies. And mainly how to make that electricity to use that SFR or existing large scale of the right total reactor or other systems. But the point is that those kind of the generation are corrected to the kind of the carbon recycle. For instance, to directly generate that hydrogen or directly use of the heat to the industry to capture and recycle the carbon dioxide. We say that CCUS, carbon dioxide capture, utilization and storage techniques. But it's just a start to discuss about those kind of the systems. We do not have any good dissolution, one dissolution about that. And also from the viewpoint of the natural resource recycling, as I already mentioned that we need that first reactor cycle coupled with that right total reactor to manage the total amount of the spent fuel. That's also that issue from the security. And flexibility, sorry, flexibility. As you know about that, if we apply that renewable energy systems, it buries in a wide range, not only the seasonary, but also the daily. And of course, for instance, from the viewpoint of the application of the nuclear power plant, maybe for instance, the load following operation of the nuclear power plant is a one possibility. But from the viewpoint of the techniques or base load, at least I do not think that it's a good solution. But anyway, we need those kinds of flexibility if we take into account the renewable energy. And sorry, last, this is my presentation. And currently, not only the energy field, but we think about the contribution of the first reactor to the non-energy field. That is most one is the radioisotope production. And as you know that if we apply that the first neutrons, we obtain that efficient production of the radioisotope. And for instance, this is one example of the actinium to 25 and it's half life is around the 10 days. And if we apply that some chemicals connected to the actinium and this chemical is dominantly captured by the cancer cell. And we can make the efficient alpha-ray medical uses inside of the body. And we already make in the medical field, they already start those kinds of systems. And from the viewpoint of the supply, supplier of the radioisotope system. The first reactor may be coming one of the good contribution. So that is a current situation of Japan from the viewpoint of the especially the sodium first, sodium crude first reactor. So, thank you very much for your kind attention. Okay, thank you very much, Takata-sensei. We have time for some questions, any? Thank you for the minute thing lecture. So, you mentioned that Japan is going for pull type, sorry, I'm called reactor from loop type. And among these two, which is the better option, I mean, which is safer and which is the possibility to be deployed in the future, pull type or loop type? Yeah, for instance, from the viewpoint of the, let me say that in a loop type, we make that the large type of the reactor. And it may be possible. But from the viewpoint of the pull type, we still think about that not so large type that's coming from that seismic issues. But from the viewpoint of the technology, maybe for the interest of the pull type, we have a good collaboration to the, for instance, in the French or United States or many countries to share the knowledge and which resulting in the deduce of the construction cost. But anyway, I think that maybe that large type will be at the loop one. And medium type will be a pull one. I have one comment just maybe you remember that like about eight years ago, Japan decided to abandon the JSFR Japan's volume called Fast Reactor to end to join France with their Astrid development of this technology. Just use this collaboration with France on disaster. That time I told that it's very risky to rely on the foreign country to give this crucial for the national, you know, sustainability energy development to give it to the hands of any other country. And now we see the results of that. France also abandoned Astrid or postponed it for 50 years, also 30 years maybe. And now you have to like restart from the, or rely on, now you're trying to also understand that to collaborate with the U.S., like Natrium, something. What about to restart national program on Fast Reactor? Thank you very much. It's a very good question, but it was easy to solve that. As I mentioned that from the viewpoint of the budget, from the, in terms of the national, national, I have to say that the government issues, it's still quite difficult to keep the sufficient budget within one country. And in that sense, of course we need to make our own development, but still we, I think that it would be necessary to share with now only the knowledge but also some kind of the budget. That is a current situation at least in Japan, I guess. Okay, thank you. We had a question from Chad also that, from Professor Artisiu, by the way, you noticed that the joy is now under licensing process. When is expected to be again in operation? Just to give us, I understand it's not really. Yeah, at least JEEA thinks that maybe that two or three years later it start operating. That means that from the viewpoint of the irradiation test, JEEA need to restart as faster as much as faster. But maybe now it's just processing the de-dicensing and they will have another licensing issues when they make some, not the construction, but some modification. And sincerely say that how many years it takes. But we hope that within two or three years. Okay, then I know we have several questions. One is what is the current status of ESFR, which is probably not to you, but to, I think Christian will later can explain. Another question, can sodium replace water in BWR as a coolant? Can sodium replace water in BWR as coolant? Probably potentially it can be used in the secondary and in the other loop, but not of course in the main. Okay, and then can sodium be used in both primary and secondary circuits in SFR? It's exactly how sodium is used in primary and then in secondary or we say intermediate loop. And water is in the third circuit. Okay, so any other questions here? Thank you, Takata sensei. You said about Japan's energy independence and how nuclear is important in that aspect. But what about the uranium production? Because I imagine that Japan doesn't have much uranium reserves. So how is the independence aspect of nuclear regarding importation of uranium? Okay, thank you very much, that's a good point. And from the viewpoint of the uranium production from the mine, of course Japan do not have enough mine. But from the viewpoint of the spent fuels of the right-water reactor, we already have some stocks of the uranium coming from the existing right-water reactor spent fuels. And maybe that means that if we use those existing fuels, maybe we will have the thousand years resources when we are priced at past reactor systems. Please, I think this is it. But just for the mix of energy in Japan, it's well known that in Japan, you have a lot of geo-thermia on Zen, but not only on Zen, maybe. Why there is not more developments of geo-thermia in Japan? Because you have a great advantage in other countries. Yeah, actually, we have that many hot springs in Japan, but from the viewpoint of the technologies, maybe we do not have efficient systems of the total electricity. And maybe, for instance, using the geometric heating, we can make that small type generation or middle type generation, not that we cannot obtain that huge amount of electricity from the geometries. And the other thing is that many of such a good location is National Park. Okay. And for instance, in some cases, and people, especially people in Japan, so they are welcome to make that hot spring placement, but they do not welcome to make that geometric heat systems. That is another reason. But anyway, so not so good, total amount will be achieved by using that geometric. Yeah, but with the wind energy and many others, we can have a good contribution. Yeah, at that moment, for instance, public think that maybe they could have another recycling by putting that hot spring locations. Thank you. Thank you very much for your very interesting presentation. So, one question. If you have last question from here, from the audience, I don't see. Okay. Christian has a short question, and I will ask Takata-sensei to give a short answer. Yeah, okay. Okay. Now, what about ADS in Japan? Ah, yeah, actually the JAA, some of the JAA still continue to make that technology development of the ADS. And actually the ADS itself is that one candidate of the innovative systems in Japan. And from the viewpoint of the safety, ADS has a great advantage of sub-criticality. But from the viewpoint of the, for instance, as I mentioned that the plutonium reduction, it has not so good efficiency. But still, Japan take into account that one candidate from the different, take the candidate of the ADS itself. Thank you. No worries at all. Thank you. Okay, then now let's have a lunch and we come back at 2 p.m. sharp, please, okay? No delays.