 Доктор Александр Бычков доделал кучу нуклеофилосайкалов. Александр, пожалуйста. Доброе утро, дорогие коллеги. Сейчас я бы хотела дать информацию о моем любимом суббекте нуклеофилосайкал. Я сказал в первый день, что в последний месяц, в конце октября, я был в нуклеофилосайкале в 40 лет, потому что моя диплома тоже была соединена с нуклеофилосайкаловым сепаратом Литиом Айзотопс. Это очень интересное, в начале 1980-х. И позже я делал много-много использований на рейтах, рейтах-сайкала, рейтах-сайкала, рейтах-сайкала, трансмутация, и так далее. Мои экспертизы, рейтах-сайкала, специфика в моем институте, в которой я работал 29 лет, Республика Института атомических реакторов в Дмитрию Град. Это один из комплексных институтов. У нас были 6 реакторов, большие в Азии, Материал-санкт-лаборатория, специальный комплекс для производства айзотопс, производство Калифорниям, это только два производства Калифорниям в мире, Окридж и Дмитрию Град. И, конечно, фасилит, производство МОКС-фюел и пара-кемикал-репроцессии. Это был уникальный период. Мы в Советском Союзе, и в России. Это только одна организация, которая действительно работала с Паур-Грейт-Паутонием, амирит-сим, и так далее. И я работал в фюел-сайкл, много-много лет. Я помнил некоторые очень простые вещи. Мы, как обычно, понимаем фюел-сайкл, традиционный ход для маяния ураны, для приобретения для сочетания фюел-сайкл, конвершин, сочетания, или, возможно, из-за природа для стольных реакторов за белью shareholders. Фюел-фабрикация, с помощью фюел-сайкацкого на кафе ураны, и luggageусси на кафе ураны, которое тоже может includo есть сочетания. Как обычно, мы на фюел-сайкл Это все операция с пио-уренемом, или в будущем пио-ториум, и с вершином все операция с риодетами материалов, спенфюйл, паутониум, а потом, может, с минуточкой ночи. И, конечно, сейчас у нас есть два философии из философии на философии для урениума. Я бы хотел поделиться. Один философий, открытый философий, и закрытый философий, когда какие-то продукты после урениума должны быть recycled в этом системе. Итак, если вы напомнили о моем предыдущем лекции, то шею философии и электричество, не так много, но все патты в нейротеке очень важны. Без философии мы не можем получить реакцию, и мы не можем получить нейтрон, не можем получить электричество. Так что философий тоже — один из... ну, часть нейротеки, нейротеки, нейротеки, нейротеки в сверху. И, конечно, философия и философия в сравнении с нейротеки, есть больше философий и системы. И, конечно, в сравнении с реактором. Реакторами more often and I would like first part of my lecture to demonstrate some trends on the basis of last 20, 30 years where slow implementation of some innovations give real result in economic and safety of fuel cycle. Of course, I would like to underline safety. Oh, it's improvement of fuel cycle. First of all, nuclear safety is key line, a number of nuclear fuel cycle, fuel and fuel cycle aspects of course affect on nuclear safety in different meanings of this point. Economics, it's also very important, non-proliferation, unfortunately production of weapon great materials, it's belong to fuel cycle and resources, resources for future development of nuclear power. Of course, from point of view of safety, we should consider two aspects. First, separational safety, it's using of nuclear fuel and nuclear reactors and so name long term environmental safety connected to spend fuel and its specific. You know, I think you know the traditional technology for production of pellet fuel for reactors, which is usual all reactors, not all reactors now under operation with pellet fuel, but it's more than 99%. Maybe some fuels for research reactors and mainly research and pilot reactors can work with different type of fuel. It's traditional system, understandable system, a lot of plants in the world that can produce fuel. Experts and specialists who works in this area continuously works in two specific points. One is quality control, improvement of quality control on the all stages of production of fuel. And next, fuel improvement. Improvement of quality of fuel and its characteristics. Very interesting picture. The agency every five years published, collected and published data about fuel rods failures in nuclear power plants. We have not yet officially published data regarding the period from 2016 till 2020, but you can see this tendency during the last 35 years. The drop of failures is really impressive. And the idea of some companies type of wisdom gauss 12 to reach so name zero filer is really ambitious, but truly speaking it's possible to find decision then fuel will work without any failures. Here is direct effect to safety of reactors, not from point of view of server accident, but taking into account release of radioactive gases and some accidents of those three levels. And big effect for reduction of the activity of low level and medium level waste from reactor. So specialists in the fuel works in area of improvement of current fuel fabrication, for PWRs, PWRs, BMK, VWR, pressurized water reactor system, light metal, fast reactors, all others it's old fuel. And main lines for improvement now, extension of radiation period. It also has very important effect of economic and if you have reloading period 12 month or 18 month, of course in that case the loading factor of reactors could be increased and increased. So high burn up also connected with these factors and economic factors. Of course the fuel is more expensive, but the growth of fuel price is less than benefits from this new fuel. It's very important point. Burning up servers, it's also very important additions for establishing more reliable radiation behavior program. And of course increasing coefficient if you would like to have high burn up and extension of radiation period. And new line, very important line after Fukushima accident, a lot of experts in the world facilitated the subjects of name accident tolerant fuel. If taking into account history of fuel development, we can find, I can say that now no new technological ideas. But it's mainly all different ideas were generated in 60s and 70s. But industry is industry. Industry is very conservative system. Uranium dioxide pellets, quality control and work. But if you would like to avoid some strong effect during loss of coolant accident, of course it's much better to implement some more stable fuel that can work in the future. These accident conditions without any effect to release of radioactivity and so on and so on. Of course this fuel would be useful for generation 4-2. And now in the world we have a lot of activities and the big radiation programs continue in US and Russian Federation. Key manufacturer of fuel in the world continue this activity. OECDNIA published some years ago very huge report about analysis of different conceptions. But I will not explain in detail. Second point related safety of fuel cycle. Of course connected with disposal of radioactive, spent fuel or radioactive waste generated after reprocessing of this fuel. I see this picture as minimum twice in your posters and our colleague also mentioned this important picture. If we can remove from the fuel before disposal minor actinates and plutonium, we can reach some name. Radiological equivalent of radioactivity with uranium ore after 300 years of life of this high level waste. Plutonium recycling can give us 10,000 years but decreasing dropping of the activity in spent fuel and used fuel. After direct disposal it's close to million. Of course 10,000 million it is not predictable from engineering point of view but 300 years. Till now we have some burials with very dangerous things. For example after some epidemic in Europe that truly speaking cannot affect to population now. This is one of example. And taking into account Egyptian pyramids and some ancient monuments. It's possible to predict behavior of materials during this year. Of course optimistic Vladimir. I can say as chemist technologist for example have solid fuel. Each cycle of reprocessing will give us losses of minor actinates and plutonium and truly speaking this life will move slowly. But it is a key tendency. A lot of experts working in this area for reducing of so-called burden for future generation. So next point very briefly to avoid production of high enriched uranium and weapon grade plutonium. Of course here enrichment factories and reprocessing facilities can be centers of production of these materials. And so here as usual in the world we use so-name institutional approaches to avoid any unauthorized production of these materials. But unfortunately in history we have some examples. Some countries were not signed a nonproliferation treaty and start the nuclear program. But in the agency and in INPRA also we try to develop some criteria, some system for evaluation of reactor and fuel cycle system for avoiding of production of high enriched uranium and plutonium. Next economics. Economics of course connected to whole part of fuel cycle from mining till operation. I mentioned some effects. And so here I would like to briefly explain that during last 40 or 50 years we have relatively good tendency in uranium exploration. Very specific change of technology in area of uranium mining by in city leaching technology improvement of process for enrichment. I also will explain. And of course development and improvement technology for fuel manufacturing from reprocessed materials uranium and plutonium. And of course MOX fuel is one of key technology not only for current recycling but for future fast reactor technology. And of course generation 4 reactors demand advanced fuel technology. I will explain this point in some details. First of all uranium exploration. If consider traditional system for exploration of uranium accepted I think till 80s 1980s. As usual it's traditional geological studies with expedition and so on and so on. But now we have so sensitive equipment that can be used for analysis of radon on different layers and if we can find some increasing of radon content in the air. Of course we can say here we have some probability that here we have thorium or uranium deposits. It's really big chemical effect in comparison of old technology. Geophysical methods including radiometry and some other other things. And so I worked in nuclear industry many years I remember in 80s and 70s many people told about we will have not enough uranium for development of nuclear power. But taking into account new geological studies investigations now we can understand that during next 50 40 60 years we have enough uranium for nuclear power. Taking into account very interesting effect. For example now we consider some mining places is very expensive. But after initiating coal mining process and production of uranium concentrate the prices can drop. Next very important but I think it's also revolutionary step. It was not visible from point of view of mining methods. We had in history open pit systems in the world we have a lot of places where till now these places should be remediated underground system. We have a tunnel extraction of some ore but I would like to underline that the ore with 1% of uranium it is it's rich ore. So uranium it is not no it's it's element distributed in geological formations and it has no some concentrated systems uranium and thorium. From point of view of so-name quark the content of these materials in air core they is not for example bismuth bismuth maybe it's more has less quark than uranium or thorium a little bit for good. But some elements that we have in the practice manganize maybe also has the similar content in the of core maybe. But here is technology of in city leaching there some special tubes pressed chemical solution and dissolved uranium and some other elements and important point. 14 years ago in the report of the agency we fixed that only 28% of mine uranium was produced by this environmental attractive technology. But now we close to two-thirds of production of uranium by these methods. Kazakhstan Uzbekistan some new mining facilities in Africa. Canada also changed the technology. And step by step we avoid very specific and long term effect on environment. Till now for example in Soviet Union we had a lot of places for open pit mining and after completion of this activity the tails were covered by special systems. In the beginning of 90's after destroying of Soviet Union all these systems stayed without any security and we received two effects. The standards related environmental protection now more stronger but from other hand many local people try to find some metals some scraps in these areas and these areas were destroyed and Commonwealth of Independence States European Union support to remediation of similar things. But if we will use this technology of course we can reduce drastically the problem related environmental effect of uranium mining. Good tendency. Next point in enrichment. Currently in historical enrichment process it is 25% or 50% of fuel cycle. All fuel cycle. It's more expensive. Why? It's differences between uranium 238 and 235 taking into account the six atoms of fluoride fluorine. We have very, very small separation factors in any technologies. But we have very good features of uranium to have gas compound uranium gas of fluoride. And of course first facilities. I lost one slide. First facilities include the so-called diffusional process. Diffusion of gases from membrane and separation by these processes. It's necessary. For example to reach 4% of enrichment it's necessary to have 1500, 400 procedures. So it's necessary to have very big cascades, system for operation of these cascades and to receive. And a lot of electricity for gas diffusional. But from other hand centrifugal process also was calculated, suggested. But unfortunately during very long period the world industry had no system for very precise mechanics. Mechanics with graphite centrifugery. But step by step and now we have very interesting picture. First of all I would like to underline that centrifuge process is very cheap from point of view of consumption of electricity. Gas diffusion plant as usual had power plant near. For example in France, in some first facility in Soviet Union. But centrifugal process request very, very in comparison of gas diffusion process for one unit for separation of uranium. More than 500 times less. And so slowly industry change this process and if compare 2000 and 2015 in 2000 the uranium in region market covered 50% by diffusion plant, 40% by centrifuge and 10% it was excessive weapon grade uranium. Last years we on the market receive mainly only uranium reached by centrifuge. It's from point of view of economics it's one point. But another it's very interesting effect. If you have cheap centrifuge systems, a lot of cascades, very good mathematical models for operation of these cascades you can use their depleted uranium after diffusion plant with content of 0, 3, 0, 4% of uranium. Not 0, 7% but 0, 4%. Of course maybe it is seems not practical but you can avoid the process of mining of uranium. Also expensive process for conversion of uranium to uranium hexafluoride plus we in the world have a lot of stock piles of depleted uranium. And Rosatom for example now has this program. First of all Rosatom works with Rosatom's tails in Siberia. And some years ago Rosatom start program for enrichment of tails from Germany, formally from Germany. But if take into account some specific market swapping system that service connected with Japan partly with some other countries. So it's very interesting business decision that can give chance to use very big stock piles of uranium hexafluoride. And next line recycling of spent fuel. And this very important point that's related not only to economics, it's related to safety, related to environment and related to public acceptance and other things. Тruly speaking we have relatively clear history in this area. In the world we have not first of all high burnable fuels. So this fuel is not so easy for reprocessing from point of radiation state, reduction of wastes. But from other hand in any case no many countries had regular commercial experience for reprocessing. France, Russia, India, Japan, small factory and new plant is not fully in the operate. UK unfortunately stopped their program. So, and in recycling we should consider three basic tendencies. It's also Michael X mentioned its direct disposal, disposal after recycling of plutonium and disposal after recycling of plutonium and minor actinates. As you can see here the decreasing of content of, not content, it's a volume of fuel waste for our repository. Currently it's demonstrative picture with Russia, UK, Japan and India with some reprocessing plant but more advanced plant now under operation in France. It's classical example. I really like this picture. It's demonstration of work of French specialist to improve waste treatment and reprocessing plant. We've taken into account design of UP free plant reprocessing of light water reactor fuel. Of course it was initially suggested to have a lot of different type of wastes, different type of matrices. But finally they decided to make concentration of medium level wastes till high level wastes and to produce glasses with orange and all other things technological waste should be compacted by pricing. And you see now the volume. It is not radiative activity of high level wastes in large plant. It is less than one quarter of volume of initial spent fuel. It's also good tendency. No many people knows but regular work in area of improvement of nuclear fuel facility as usual can give very good and important results. Some words about recycling and non-proliferation. Here it's also very important point from point of view of agency due to recycling of separated plutonium, should reduce risks, avoiding of accumulation of spent fuel also should avoid risk of production and using of plutonium for other systems. So we have of course some dualism in the world. Some states decided to has open fuel cycle but recycling can give more advances in comparison of direct disposal. We would like to underline very excellent experience of French industry on recycling of plutonium. Of course initial conception was connected with fast reactors but unfortunately national program of friends postponed fast reactors now. But instead of these French companies, they have maybe not so advanced factory but very stable production line for most fuel and taken to account the current fleet of French reactors. In neighbour countries plus very small flows in Russia for the end 800. Now it's around 5% of fresh fuel market covered by MOX. Now taken to account Japanese fuel to citizens. Step by step, step by step 5% in this market is relatively strong line. And this studies continues. In France experts especially try to modify MOX fuel in more advanced fuel assemblies, fuel radiation system for one of key line to increase of plutonium loading into reactor. Russia taken to account specific of there in comparison of classical PWR works in area of so name remix. That is where is uranium slightly enriched. So it's combination of reprocessed materials, so name remix. And also Russia has now very strong experience to recycle uranium too. Initially it was developed for RBMK many many years ago. Then fuel after mayac can be used for RBMK production. But now it's more advanced taken to account some process for reenrichment. And I can say some words about that reprocessing recycling. Recycling now it's industrial options. It is not only research and development and 40 years experience of reprocessing in France. MOX fuel ability to load till 100% of MOX fuel. Russian program for bayonet 800 is some restoring of MOX production in the world and new tendency to use in this uranium for thermal neutron reactors. 10 минут. I have long presentation but tomorrow I have also 45 minutes for lecture about legal institutional aspects. But this lecture is very brief. It's around 20 minutes only. And so part of this lecture will be given tomorrow. Okay. Generation 4. Tendency and fuel for generation 4. This table you see this table yesterday or day before. We have a number of six reactors. I did not include here other systems. And you see four reactor systems should take closed fuel cycle. One system is optional closed fuel cycle supercritical reactors. And only one system is considered without closed fuel cycle. So here it's interesting picture where they demonstrate what temperature and what irradiation effect we have for materials and of course for fuels in different systems. Of course in comparison of current fleet of reactors the temperature is higher. Irradiation effect is much higher. And so we should have some selection of new fuel. Of course we have in history a lot of candidates. Different type of ceramics. Nitrous, additional dioxide, nitrite, carbide. Different type of metal alloys. Uranium, plutonium, uranium with different elements. Some specific system with mix of ceramic metallic and different ceramics. Type of for example plutonium with so name inert matrixes. And molten salt, mainly fluorides. So we have this selection. But what we can use for realization of closed fuel cycle or fuel cycle for different generation 4 reactors. First of all sodium fast reactors. Not truly speaking. I think the key problems around these reactors from point of fuel and closed fuel cycle. In my opinion soft. We have ceramic fuels. Uranium, mox oxide, mix nitrite, metallic system. Аквастехнология, mainly for oxide fuel. That can be realized not only as separate for this fuel. But for example we have good experience in luck. And limited experience in... Okay. And limited experience in Mayak for reprocessing of the mox fuel of fast reactors. Sometimes it's possible to add these materials to main stream. For example, I know the history of reprocessing of not irradiated fuel of SNR 300. But that fuel contained high quantity of amurids. About 40 to 20 years storage. But Kajima or Areeva completed it. And fuel fabrication technology also exist. Pellets, vibroparking, injections. Melting. Not melting, injection casting. High temperature reactor, it's last. Lead cool fast reactors. Also closed fuel cycle. Mainly ceramic. Here it's some specific of possible interaction of metallic fuel with lead. Or lead-vismont has some limitation. Also it's possible to use aqueous process if you have a big facility. Or maybe pyro process if you have no big facility for reprocessing of fuel. It's possible to make some process for preparation. As usual spellet or maybe some type of ceramic elements. Gas cooled fast reactors. Also has the same as for other fast reactors. But here more dense ceramic is usually considered. Not oxide, but nitride. Or maybe carbide in future. So supercritical reactor. From point of view it's very close to light water reactors. But of course I think for reaching of expected characteristic. It's much better to use some more advanced ceramic materials. And maybe it's one of the line where it's possible to use vibra packing fuel. And of course aqueous process is main and pyro process is one of. High temperature reactors. Of course we can use here uranium, uranium plutonium, uranium thorium system. Uranium, thorium, plutonium, thorium, plutonium and some other. Here we have very good things. It's very high burn up. Very high burn up of fuel. But fuel is very complicated. And truly speaking it is not easy for reprocessing by some conventional methods. Of course we had some mind games around pyrochemical process of this fuel. Truly speaking it's possible. Truly speaking it's possible if it will be needed in future. And final line molten salt reactors. Close fuel cycle. But molten salt reactors is close fuel cycle itself. It's here we cannot speak about reprocessing methods. And fuel fabrication methods. It's only one thing. It's pyro process on site with this reactor. So I worked in the area of implementation of vibra pack fuel many years. Unfortunately we had not win competition with pellet due to quality control systems. Taken to account cladding bought many, many years ago. And related quality control in our facilities. But this fuel for fast reactors is very interesting. It's more flexible. And after radiation this fuel has similar structure as for pellet fuel. Here is our experience. This is old pictures from treat experiments of Oak Ridge National Laboratory. Also very unique fuel. It's trisoparticles. It's traditional with uranium, enriched uranium dioxide. But in the line of accelerated tolerant fuel. Some particles with uranium nitride covered by different layers of carbon. By pyrographite and carbon silysid. Silysid also can be used for high temperature reactors. So, Vladimir, I would like to take some words about reprocessing. Advanced reprocessing. Now we in the world in main reprocessing facilities we use a name purex process. That was developed for extraction of plutonium from spent fuel. Of course it was modified. For example in Mayak my colleagues works with separation of neptunium in some special line. And this process is very good established. We can count some specifics. For example for extraction of minor actinides from one side. And from other side tendency to have one flow of uranium and plutonium. One flow of uranium and plutonium. Some methods were developed in the world. So you can see the map of this acquisition methods. Other methods is pyroprocessing. Two years ago agency published status and trends in this activity. And for example this picture is one of step of reprocessing of uranium plutonium cerconium. Or uranium cerconium alloys where is spent metallic fuel in molten chloride salts. And used as anodic system. And after dissolution parallel it is continuous process. Can deposit uranium metal. Or plutonium can be also precipitated. Electro-deposited to liquid cadmium cathode. So in that case we can restore physical property of these materials after future casting. Purification of casting. The similar approach can be used for nitrite fuel. Due to nitrite also has electroconductivity. Relative electroconductivity for anodic dissolution. I walked many years process of pyroprocess for oxide fuel. It's more complicated. It's necessary to have process for dissolution of uranium and plutonium. Or spent fuel in molten salt by chlorine with presence of carbide. We use some changeable crucible from pyrographite especially developed for this system. We can produce after mox or uranium dioxide or precipitated plutonium as cathodic deposit. Here is also very interesting effect of uranium. Uranium dioxide is semiconductor higher than for degrees and degrees. So here we can organize so name flat growth crystal system. И after that this material can be treated for removal of salt by vacuum cleaning or washing. And after cutting can be used for vibropacking. Here it's my picture. I'm offer of this picture but it was especially right 30 years ago for presentation in Japan. Of our process in comparison of America. It was my first visit was in 1992. Yes it's agonist laboratory process. Cutting of metallic fuel after radiation. Pyroprocessing for removal for extraction of uranium plutonium. Casting of fuel and fuel pin productions with layers. Only some steps. It's only one, truly speaking, one chemical process. Truly speaking it is not full scale reprocessing. It's restoring or refurbification of fuel. Restoring of physical state. And the similar for oxide fuel. Декладинг. It's very unique process for high temperature decladings. You still have no attractiveness in liquid form with oxide fuel. And you can drop steel separately and receive fuel separately. Of course it's relatively expensive and very high temperature. Next step. Parachemical electrovining process. Дисселюция and electrochemical deposition. Crush of this cathodic deposit. Removal of salt. And production of fuel by vibroparking. And we have short brief close fuel cycle with pyroprocess. Of course we have some tests. Not very high but very unique fuel. For example fuel after bore 60 with radiation. With average burn up more than 21%. 20% of fission products. But it was possible to receive materials after pyroprocess. And we had a radiation program for some fuel pins after this reprocessing. So. And some words about activities of the agency in area of advanced fuel cycle. We have now study completed. It's not improv, but it's my colleagues in nuclear fuel cycle section. We have consideration of different approaches to fuel cycle from point of view of optimization. And I would like to underline mainly this study. It will be published soon. Existing in advanced nuclear fuel cycle technology options for waste burden minimization. We consider current technology and some tendency to improve and improve and improve. Till full partitioning and transmutation systems. I am also the co-author of this reactor. And last slide of my today's part. Реактор. Реактор and fuel cycle in one unit. First of all it's liquid fuel. Mainly fluoride. For thermal neutron people consider it chloride. But from chemical point of view chloride is more aggressive systems. From point of view of corrosion. So it would be no easy to find good materials. Технология of welding of these materials. And for this system next secondary circuit also could be used molten salt. Molten salt has very big capacity from point of view of thermal accumulation. It was different conception of fast reactors can work as breathers, as incinerators. Or sources of neutron, as we saw in one of presentations. And octinides could be dissolved in this system. And this system should have some online chemical reprocessing. May be during long period it's possible to operate without full reprocessing. For example only removal of noble gays and some noble metals. And add some fissile materials, plutonium, or mine art, and so on. And to start full scale reprocessing. For removal of full extraction of partitioning of some out of fusion product. May be after 10 years of operation of this reactor. May be after 15. With little more to start reprocessing after 15 years of operation of plutonium incinerator. Molten salt reactor, lead by accelerator. So, and I mentioned yesterday the project synergy where we in the agency discuss about current approaches to fuel cycle. Result of current research and development as next step. And we are expecting of some fruits of tomorrow research and development. So, this is last slide for today. And of course the philosophy of close fuel cycles now has very interesting reflection. In the area of United Nations system we spoke about circular economy. Close fuel cycle, it's really circular economy. If taking into account some specific, some specific idea for recycling of cerconium. For using coefficient product for different tasks for irradiation sources and so on. Really we have one of example of circular economy. Next, my part, it will touch some national policies. And some legal aspect of internationalization of fuel cycle. But I will connect it to these parts with my tomorrow's lecture. Sorry. My favorite subject. Thank you very much. So, we have time for the questions, comments. Thank you sir. So, how much percent of the fuel is recycled in general? In the world? In general. In general? A lot of years has been spent. Now it's less than 25%, but more than 20%. I have no direct information for current situation. But for example, in 2005 we had 25% of repossessed fuel. It's taken into account all flows of river, 440 in Russia. All Magnox and partly Lightwater Reactor fuel in the UK. Taken into account some overseas contract with Japan. Very huge program in France, French reactors from Germany. Old Italy systems, Netherlands, Belgium, partly Spain. And of course German. German has big programs. Plus old experience of US till 1977. Experience of India for heavy water reactors. And limited experience of China. But China now works. So, it's more than 100,000. I will check and will reply tomorrow. More detail. Okay, Dr. Lace. Thank you Vladimir. Thank you Alexander for your very interesting presentation. I am not an expert of this fuel cycle and repossessing. But that was a good question. What do you think about the strategy of what we call multi recycling of plutonium in lightwater reactors? In order to delay, I would say, to delay the development of fast reactors. Ну, first of all, I remember good lessons of Massimo Salvatore, who explained that two cycles is maximum for conventional plutonium after lightwater reactors. Taken into account that now we have growth of burn-up, the quality of plutonium dropped. But, I mentioned here some studies in France and in Rosatom, for using of plutonium for multi recycling of lightwater reactors. Here, it's idea to decrease content of plutonium, but increase of enrichment of uranium. In that case, they understood, I'm not physicist, we have some effect of compensation. And in that case, for example, for remix fuel, we consider it as minimum four cycles. It's possible. Of course, here is necessary to make some corrections. And in any case, it will be not very easy task. To truly speaking, we have different plutonium in each new fuel assembly after reprocessing. And sometimes, I worked with reprocessed plutonium. Every container has some deviation in isotopes. Sometimes, especially in 41 and 40, it's one or two percent of deviations. Абсолютно нет. И так, я думаю, что старая концепция, когда системы термонутронных реактов, и быстрые реакты, работают вместе. Один рецикл в быстрых реактах, и два рециклы. Один рецикл в термореактах, и два рецикла в быстрых реактах. В этом случае, мы получаем эквилибрию изотопичного композиции. И эта плютония может быть использована для термореактов. Но это компликатический систем. Это старые концепции. Но это возможно. Спасибо. Спасибо большое. Присаживай следующее. Спасибо еще раз. Пожалуйста. Так, если вы посмотрите на концепцию этой идеи, как исследователи, как инженеры, то идея этой цикловой цикловой циклы, конечно же, но всегда есть другие люди, которые любят брать какие-то brilliant ideas, экономисты. Так что, можно ли вы briefly provide any information about economic aspects and economic differences between closed and enclosed cycles? Потому что, как вы знаете, some countries accept only brilliant ideas decided to use an enclosed cycle. And, of course, they have some reasons. If short reply, the expenses for open fuel cycle and the expenses for closed fuel cycle are comparable. It's a similar level. But now we need to change the paradigm of evaluation of this system. Nobody can understand the expenses for a whole cycle of control and monitoring of spent fuel disposal. But we have experience to work with high-level waste without actinates. Here we can predict using of separative materials, can predict behavior of end expenses for high-level waste. But we cannot predict correctly all expenses for open fuel cycle. Yes, unfortunately, we have no initial data for full scale nuclear energy system assessment, as I spoke yesterday. Yes, yes, but this idea is comparable. So, we are coming back from fuels with energy.