 Потому что я все-таки хорошо, но есть несколько онлайн-лекторов и людей, которые ждут для нас. Может быть, они не имеют эту красивую кофе, как мы. Окей, добро пожаловать и давайте начнем. Я снова начну. Я покажу вам небольшую презентацию на оборудовании инновативных реактов. Мы получим много информации об этих реакторах в этом неделе. И я просто покажу вам. Во-первых, я расскажу о классификации, о том, как мы делаем это, и о том, что происходит между дживом, терминологией и айетерминологией. У нас есть несколько новостей. Мы покажем экологические и физические соперники, которые описывают истинные реакции, и ее финициация. Я покажу вам 6 дживов, 4 реакторных концепций. И также покажем вам простые статусы на первых реакторах. Каринт статусов на первых реакторах. Генерация для интернета-формы – это большая организация, которая соединяет в несколько странах, которые интересуются в развитии инновации. Генерация для реактов. Они definят, как Генерация-1 – «элио-прототайпс» и «демонстрация планов». Это первая нуклеопарная плана. В нуклеопарной реакции есть генерация 2 или 3. И ванной нуклеопарной реакции может быть эволюционерная и инновативная. Вообще, эта генерация 3, 3+, 4 и 4 может пересолить к эволюционерею и инновативной реакции, как defined by International Atomic Energy Agency. Мы делаем эволюционерную реакцию. Это реактор, который передаёт реакторами, в котором маленькие изменения в дизайне, просто эволюционерные изменения. Несколько новых технологий, которые они используют, за то, что они называют «высые реакторами». И потом, реактор, как генерация 3, как генерация 3+, как генерация 3 и 4, же на commonly known sites.שובативные реакторные дизайны, которые reactions to generation 4, в GET-от APR. И в этом случае SMRSmall and Medium-sized or modular reactors, whether it is either evolutionary or innovative. Эволюционерные, которые прототайпи were already done for the transportable units. в России и других. Это визуальные дизайнеры. И есть несколько инновативных дизайнеров, которые используют различные кулонные и различные технологии. В деталях вы можете проверить в айе-адвансных реакторных информационных системах Ares, в котором есть линк. Или вы можете просто просмотреть все эти адвансные реакторы, оба инновативные и визуальные. А также это терминология, которая зависит от времени. Что сегодня инновативное, может быть эволюционарий завтра. Что сегодня, может быть просто эволюционарий завтра и так далее. Генеральный третий более-менее как картинный систем. И эволюционарий инновативный, как лаграмжный систем. Вы всегда делаете эти реакторы, но, в любом случае, потому что различные страны и различные организации могут быть использованы более-менее. Ок. Если вы посмотрите на генеральную и интернациональную форму, они постулированы several goals, о которых они хотят, с этой генеральной реакторой. Система, экономика, безопасность и реальность, реакция, и физическая протекция. Итак, в том числе безопасности, технологически, генеральный пастолейт для генеральной энергии будет выявить необходимые эволюционарии. Так что, так же, серьезный accident, в котором большая религия радиоактивных азотопов так же, так же, будет практически выявлено. Практические выявления имеют в виду физически невозможно для каких-то эффектов, или очень low probability, очень-очень low, но это не обозначает probability, скажем, реактор, да, или просто очень low physical probabilities. Эти goals могут быть очень генеральными реакторами, и между ними можно иметь и эти, конечно, все эти реакторы для генеральной энергии могут быть инновативными по иеротерминологии, если нужно только для генеральной энергии 3+, как Гифф говорит. В общем, реакторы классифированы, как вы probablemente знаете очень хорошо. Извините, пожалуйста, мьют ваши микрофоны, приятного аппетита. В общем, как вы знаете очень хорошо, реакторы могут быть классифированы по мидераторам, кулам, филотам, попросам, и силам. Для мидератора, это может быть вода, графитам, реакторам, или для Fast Neutron System, мы не имеем мидератора, мы пытаемся avoiding any moderation в кулам, опять это может быть вода или мидераторам, ликвитами, гас-култ-реакторы, которые могут быть классифированы по аэрам, CO2, и хэллоуам, и молтен-солто, в различные времена. Если вы посмотрите на пилот, реакторы могут быть пилотами ураниум-диоксайд, или мокс, и микс ураниум-диоксайд, и пилотомиум-диоксайд, пилот может быть also metallic, или ураниум-диоксайд, и пилотомиум-диоксайд, и карбайц, но сейчас нитрайта, как потенциально атрактивный пилот, и молтен-солто можно опять, как кулон и пилот, по-пропорту, реакторы могут быть, как для электрикалоплики, для того, чтобы длина электричества, а также для нонеллектрикалоплики, как и для для длины, для дома длины, длины, или для техниологических процессов, для того, чтобы длина температурной длины, длины, и для других, которые не длины электричества. Для того, чтобы длина или длина, и также, может быть, то есть, Eunitry will have an lecture later after this one. So, Jeff proposes six Yeah, sure, please. I am asking about a fuel, like, now I am just interested in the Silicite fuel, so do you have Я выиграл его, использовала его для рейтинга, но не для электричных реакторов. Почему они не используют ранюм-силиссайд, как рейтинга для рейтинга? Силиссайд? Нет, нет. Может быть мы можем задать эту вопросу для... Мы ухватили эксперт Александр Брюшков на филосекле, чтобы он мог ответить. Окей. Давайте вернемся к... Есть различные типы филосеки. Что я выиграл здесь, это, наверное, самое главное. Конечно, мы можем поговорить о рейтинге Ториума, здесь и других, но там более-менее... Я не хочу сказать экзотик, но в будущем. В будущем, считаем, что в будущем. Здесь я просто представил самые-менее типы филосеки, которые уже использовались и были использованы в реакторах. Окей, если вы посмотрите на шесть... ДЖИФ предлагает шесть концепциональных дизайнов для будущих реакторов, которые очень высокие температурные реакторы, которые приготавливаются на хеолиум, в сиромальном спектру, СФР, содиум-култвастый реактор. Окей, конечно, мы говорим чуть-чуть позже. Супер критикальный водо-култвастый реактор, который может быть в сиромальном спектру, в сиромном спектру, в сиромном спектру, или полотенцом. Это супер-кратиковый водо-култвастый реактор, это необычное, но можно работать в сиромном спектру. Мы видим гас-култвастый реактор, который уrier на высоте, это в сиромном спектру, в сиромном спектру, в сиромном спектру. и температурами, и температурами для гас-култ-фаста реактора, как и для VHTR. И для култ-фаста реактора, которые также включают лэд или лэдвис-мутеотектик, и для молотон-солд реактора. Есть несколько типов, которые могут работать на сормах, на фастах, в спектрум, и на северных концептах. Это просто сравнивает с нейтронным спектром, кулон и температурами, и также требует... Какой-то филосайкал, открытый филосайкал. Классный филосайкал means all nuclear materials are redeveloped and everything is closed in... so the fuel goes either to the thermal reactors or come back to the original reactor and closing fuel cells means you don't have the waste. Most of the concepts are closed except for two, which can work in a thermal spectrum, which are not closed. This plot shows more or less this sixth concept. Maybe I believe you already know this and you know the differences between those systems. Let's say for the sodium cool, I don't know if I have this comparison. Maybe I will go now a little bit to comparison for the coolants. What are the key physical properties we expect from coolant to be considered as a reactor coolant? So melting temperature, it should be, let's say, depends on how the reactor cools down temperature for fuel handling. If it's frozen, it's one thing. Of course, it's better to have it... Lower melting temperature is better, like for water, for example. Бои... Бои-поинт, и ликви-твертая температура. Это тоже очень важно, потому что мы хотим убить бои-поинт. Мы не хотим, чтобы кулант убить. Иногда это невозможно. Для воды, для этого, чтобы увеличить эту бои-поинт, нужно применять очень высокую температуру, как 17 мегапаскаль, или даже больше. И для термопроектировки, хит-капасити, лямбдевича, термопроектировки, высокая температура, и, конечно, высокая термопроектировка, это лучше. У нас также нужно стабильность кулана, поэтому это должно быть стабильным. Для этого, пио-материал, пио-хемикамико-элементы предупредимы. Денсистия кулана будут влиять на пумпинг, пумпинг, и другие параметры, как сейсмей-бехавр. Такая денсистия, как для воды, иногда это beneficие, иногда это не beneficие. Очень важная цена, которую мы должны предупредить, это интеракция кулана с реактором, с стилами. Если оно решает коррожение мастерансфера, то это очень важно. Кемиклая реактивность с сараудованием филлюиз, как сейса, вода, органические продукты и так далее, это очень важно. Окей. И я буду... There are also several important key physical properties, which I would highlight the transparency of opacity. For the transparent, like water or gas, it is easy in service inspection, but for non-transparent it is very complicated. There are any other several others. Again, I want to show the availability of this material in nature. For example, water we have, a lot of water to do it and we have unlimited resources of water. But when we go to the vis mode, we don't know it's maybe not that many in nature and also cost is the last but not least parameter. It's not physical actually, property cost and availability in nature, but this is important properties of the coolant. So again, for the fast reactor coolants, we want first of all not to be not to moderate, so water is excluded in this case and other materials have to be used and also it could lead to if you have high absorption, relatively high absorption coefficient of neutrons, you will have void reactivity effect, means when you remove the coolant or for example when it boils and it's called void, void is means just coolant is removed, it's not actually void of course, but then you have positive reactivity effect which can affect the safety of the reactor. Let's compare the like quickly the coolant or more physical properties here presented for the all six generating system. So I would like to attract your melting point is important boiling point, let's say for water it's normally 100 on the degree C, but under high pressure which is 17 MPa, the boiling point for water is 350, it's still too low and then the reactor vessel under high pressure which is potentially has could make a lot of destructive work if you have a leakage even or breakout of the vessel, it could be potentially huge mechanical work let's say physically sane or it destruct your work in principle to destroy the environment and the reactor and still it's only 350 which also for the coolant with this the efficiency total electrical efficiency of the plant is much lower maximum you can reach maybe 30, 32, 33% of efficiency so two sorts of energy you have to lose to the nature if we talk about the sodium which higher and let and let this move even more high which is very beneficial for the let so we don't expect any boiling in case of let and let this move coolant for example for helium and other things it's boiling point is already gathered stays from this very low temperatures so we have to use the pressurized coolant in this case and for the several this is one of the examples of the molten salt it's about 1700 degrees Celsius which is also ok relatively high boiling point and we don't there is no concern about this the density compared to water ok sodium is nearly slightly less density than water however let and let this move higher and heavier than water helium is also lighter than water and get essentially is open very very light but under high pressure we go for 20 mega Pascal for helium it can reach like 8 kg per cubic meter which is ok and molten salts are very dense so means you need a lot of power for pumping of this reactor so and another parameter properties physical properties is heat capacity and here specific heat capacity per kilogram you see that water is the best the best coolant so higher heat capacity less coolant you need to remove the heat from the reactor ok very simple in this case water is the best of course and also helium is good if you take by kilogram but what is also important this volumetric heat capacity means how much volume of the coolant you need to remove this not kilogram because at different density how much volume of this and then it defines your velocity of the coolant in the reactor so for water is also very high and is again the best heat capacity while for this by the comparit like you see if you have specific heat capacity for lead it's 10 times less than sodium but if you compare with volumetric heat capacity it's better than sodium in this case so you need less velocity to remove heat from the reactor with lead or advisement than with sodium but still you need more so water is better in this case thermal conductivity is a very important factor which is so here sodium is the best and it means that all temperatures so the temperatures of the cladding of your pin of all velocity temperatures will be lower and absolute temperatures and all maximum temperatures but also the gradients temperature gradients will be much lower in this case sodium is the best but lead and advisement also have very good thermal conductivity in case of molten salt if you take this conductivity it's very low however for the molten salt reactor also it's not important because at least in this design where this coolant is also the fuel so you don't need to transfer the heat from coolant to fuel because they are already the same thing so you don't need this and then this thermal conductivity does not play big role unless you want to remove also this heat from the coolant sooner or later in heat exchanger then it could be a problem and then to reach this air also kinematic viscosity is important factor because it shows how much delta P pressure you need to pump this coolant through your system this is quickly explained traditional actually sodium cooled fast reactors have a long history and the first reactor that generated electricity and I believe you know which reactor and when generated first electricity EBR1 EBR1 it was sodium potassium cool reactor demonstrated reactor only yes but actually that increases several kilowatts finally of the power but this was to demonstrate production of electricity and that was sodium and EBR means experimental breeder reactor so the breathing possibility already considered on the first ever reactor that generated electricity so and that was sodium potassium or alloy what was the coolant there so sodium cooled fast reactor have a long history about 500 reactor years in operation and it's mature technology we can consider here mostly the pool type reactor when you have this big pool of sodium here with a small relatively small core inside and but this is nice design and then you have ok just before I forget because sodium reacts very aggressively with water so you want to intermediate heat exchanger to avoid direct contact of the radioactive sodium in the primary circuit with water of the secondary then we have to add the intermediate exchanger and this heat exchanger is located in the reactor pool outside the reactor vessel but this is like low power low pressure volume which is more or less ambient pressure at least on the top of this reactor however this design doesn't work for the seismic areas like in Japan so in this case you also can consider loop type reactor where you have separate intermediate heat exchanger somewhere outside so there are two just wanted to say common types of the sodium called faster reactors this slide shows this history of this sodium SFRs which I say it's mature technology so we had several reactors in France experimental Saudi reactors and again experimental phoenix super phoenix was the first industrial reactor that it works very on in operation for almost 10 years it was never reloaded and was shut down in the end of last century mainly for the political reasons I believe Germany was excuse me running the experimental KNK reactor and projected SNR 300 that was also stopped in operation in Soviet Union I mean Russia Kazakhstan we had several reactors BOR-60 then BOR-350 in Kazakhstan BAN-600 and BAN-800 which I operate now in near Ekaterinburg and one two SFRs under design and construction BAN-12 is under design and MBR experimental reactor is under construction will replace BOR-60 reactor Japan developed and running the Joyo reactor which is now shut down but awaiting the license for restart it's a small experimental reactor and Japan built Monju reactor which was only working like half a year it was 260 megawatt electric but after sodium leakage accident in the same year it started and under decommissioning now in the USA as you remember we have this EBR-1 and then several other reactor in operations last was FFTF 400 megawatt which was shut down in 1992 there was a project and now it still exists VTR it's a new design and several other actually for the sodium Natrium for example we talk about this later but okay it's under design let's say not under construction in India FFTR operates since 1955 it's small experimental reactor and PFBAR then you see this commission in 2021 we also expect this reactor to be commissioning every year but unfortunately it's postponed may be good because they conduct very nice lot of tests to make sure that reactor operation is safe, there are no sodium leakage and so forth India also develops several other reactors in China already more than 10 years in operation it's CFR China experimental fast reactor small reactor 200 megawatt electric but China now builds two CFR600 reactors which is under construction and expected in few years to be built two exactly not very exactly the same reactor 600 megawatt and other reactors under design so I think I should maybe faster to complete this historical overview so this slide shows pictures of the reactors which are in operation in several countries again it's been six congress in Russia and been at congress recently since 2015 also in Russia FBTR in India, CFR in China PFBAR it's under commissioning in India expected again next year probably and that is like five main reactors under operation in the world now or expected to be starting operation in the world there are several new innovative design which can be classified as generation 4 it's been 12 hangar in Russia CFR600 in China it's this is difficult to identify is it generation 3 plus or generation 4 but it's under construction and CFR1000 in China that will be generation 4 reactor there was a project of European CFR European sodium cool fast reactor which was 1500 megawatt electric but now the power is lower and then it's like hypothetical reactor I would say there are several other but they are not really not say they are paper reactor but they develop an a postponement waiting for the political decisions and so on just to show you the evolution of the reactors and what is make its existing fleet evolutionary innovative let's say BN600 operates since 1985 in Yekaterinburg in Russia when we make when Russia made a new reactor BN800 what is similar it's similar exactly the same very similar a sodium the reactor vessel and sodium circuits basic safety systems are also the same information control systems including the reactor monitoring system are the same what is new for BN800 it has additional most important passive safety system so called hydraulic suspended control rows so when you have nominal flow control row is out of the core what when flow becomes lower and flow row automatically inserted in the core so the reactor shutdown is a new but only one passive shutdown system and of course it has numerous other improvement but still we consider Russia considers this BN800 as a generation 3 plus reactor not generation 4 it's not enough safety system but when Russia now is designed BN1200 this is already industrial side big power reactor and what is innovative this is first of all is a proven technology based on the experience of the both previous BN600 and 800 reactors however there are several additions for example they postulate that accidents that require public evacuation are practically eliminated and that is thanks to the passive shutdown system including this hydraulic suspended control rows and an additional passive high temperature accumulated control row system the reactor will be using uranium-plotium plutonium nitride fuel which is better at least considered as better and safer as compared to the mox fuel it will have is reactor core lower power density and passive decay heat removal systems and last but not least it will be competitive with other advanced nuclear power plants and with power plants that use for self fuel and of course with renewable as well this makes this design generation 4 maybe I will skip there are several cases main improvement goes to make it generation 4 it's to make sure that all severe accidents are eliminated and we can reach it using the different types of the passive shutdown system and this slide shows several shutdown systems and even in case of the core meltdown using the special dedicated core catchers we can ensure that there will no be huge or quick release of the of the radioactive material and let this move reactors were designed because sodium has very disadvantages parameter which is when sodium reacts with violently with water and even on the air sodium starts burn fire but this is not that big style like gasoline or what else but still it doesn't require any ignition so then you want to separate sodium and water and you have to implement this intermediate intermediate circuit which makes cost of the reactor much higher so if you use lead which doesn't react with water and with air violently then you can escape skip this intermediate circuit and make all the system the construction cost everything smaller and cheaper of course capacity we already discussed the beneficial properties of the lead on this case however we have a problem with lead because it's erosion and corrosion so this with lead and structural materials you have to control the oxygen level very accurately not to avoid elimination of the oxide level on the construction materials or not to make this oxide level is too big so it can be broken and it can block the flow passes also this is one disadvantage of lead and also the problem with lead it has very limited operational experience we never had this reactors for generation electricity except small experience with Russian submarines working on the lead with material tactic that is the problem but this is very promising technology and we have many numerous I would say a lot of designs of the reactors new with lead or lead with material tactic many of them one of them is already under construction is Brest OD300 in Russia but there are several other designs which are very promising LFR Mira in Belgium I am not sure it is really postponed but it is accelerated driven systems we know the people here who are working on ADS also and Amphora Shapes LFR IS to helmet reactors which is now get new investors and new plus and also Sealer 55 megawatt LFR developed in Sweden this is completed transparent to neutrons you can reach very hard neutron spectrum it is slower activity insertion chemically in air and also always the same phase already gathers optically transparent not conduct in electricity and can be applied for the very high temperature applications however it requires huge pressure because of the density of the helium and then you have to create reactor vessel with high pressure so it can be ok, the gas is non condensable also so it makes in case of loss of coolant accident could be problem and have low thermal inertia so reactor core can hit up rapidly if it force into it and also again there is no operation experience with helium at all one example of the helium reactor is GFR Allegro which is under development in Europe however it is still it is huge power reactor under development but still need to be I believe it takes more years to do molten salt reactor are very popular now because of their obvious features for example first of all natively when temperature rises molten fuel expands and then you automatically reduce the reactivity so there is no problem and also heat is released together with coolant all together interesting design however the experience with molten salt is also to be proven it's under operation so I will skip a couple of slides there is one concept which combines molten salt technology let's say traditional sodium cooled fast reactor it's a new natural reactor announced by terapower which has actually the normal SFR which is 345 megawatt electric but it's combined with storage system which is filled with molten salt which has huge heat capacity so in this case let's say when the electricity is not required reactor is working to heat up this molten salt and storage energy there and when let's again let's say in the sunny day we have solar panels which generate electricity and then the clients don't need electricity from the nuclear power plant in this case you store energy in molten salt but when night comes then you need some evening you need some electricity then you can generate electricity from stored molten salt and in this case reactor peak power can reach 500 or 600 so double actually of the nominal power of SFR this can be used for non-electrical applications and work with renewable again when you have this depending on sun so main problem with renewables of course you have wind, you have generation you have sun, you have generation and vice versa but for the nuclear power plant you won't always work on 100% of power for this if it's not required you can store it for example in this case in molten salt and this storage is allowed this reactor is announced by TeraPOW which is one of the main investors is Bill Gates and even he is very enthusiastic you see these shapes of the reactor scheme supercritical water cold reactor is also very interesting concept under development but it's not like near future I believe I just want to skip both slides because it will be explained you in other presentations and before I complete that I just want to show the challenges for innovative fast reactors also which is most of them are fast reactors fast nuclear spectrum reactors there are several challenges at present we the most of mature technologies is sodium cold fast reactors with oxide metal or nitrate fuel as well this is what we know however it seems important to develop a viable backup option such as let all this mod coolant with oxide on a tried fuel or maybe also gas coolant and with carbide fuel it was the idea which is not very popular now or molten salt cold reactors also and okay just for the sake of time just to show you the status now fast reactors in operation and under construction and decommissioning in Russia again we have these four reactors which is two of them three of them sorry in operation and beer is under construction and breath all and breath three is under construction again and in China CFR is in operation and two units of CFR 600 under construction India has sorry FBTR in operation experimental reactor and PFBAR under commissioning already Japan Mojo and Joy experimental in waiting expecting lightings again and Mojo is under decommissioning you see here almost all of them of sodium cooled reactor except breath three kind which is new this is what reactors which are real reactor which will be operating in coming years soon however if you look in the picture of the reactors under development and design in this case at least half of them are light cooled first reactors and we have also several reactors with another coolant I put it bold here we don't know which is most realistic by the way but just following the news announcement we can see which reactors have better chances to be built and deployed than others in this case you see that now the most interest is moving to the lead from sodium while sodium remain the mature main technology but lead is new under development technology in addition we have gas cooled reactors and molten salt cooled reactors and especially now we have this shift to the lower power reactors or SMRs next after me by Chariobatra so I will let him to explain the benefits and with this I'd like to thank you for your attention and ready to answer your questions please yes please but please please come here because I know we have only one microphone here that walking we want to hear the online audience as well I don't understand you spoke about a first nuclear reactor and I remember that F1 was the first reactor or you include industrial reactor we talk about the reactors that generated electricity okay there are many other experimental reactors of course also and 3 years later in Obnisk we had this industrial nuclear power plant that is already 5 megawatt electric in case of the EBR1 it was only like just to demonstrate few bulbs lamps simply it was I believe it was 3 or 5 kilowatt finally the total electric power but that was the first nuclear reactor that generated electricity please come here to ask a question and also we I know how we do it but thank you for your presentation I have a question about the best practice and experimental of the using these generation reactors as you present about the development of technology only the SFR is the only technology that have experimental data but SFR in compare with the PWR have many disadvantages also but we say that it's a generation for reactors and other design all of the other design are the showcase for a nuclear development for example I participate from 2 years ago in a new generation reactors and all of the presentation is about the benefits all of benefits but nobody talk about the challenges we have many challenges so there isn't any experimental data about these designs it's a big challenges for development and also you say that most of the designs concentrate on a LEADFAST reactor but also we don't know about the phenomena that occurred in the future for LEADFAST reactor also so I want to ask you about we need to nuclear power plant for an earlier replacement with the generation 4 past generation reactors so I want to know about your opinion about which of designs really go to the toward the best replacement with the PWRs thank you so much ok thank you thank you for your question and rising this important issue also ok I don't agree that we don't have a lot of experience for the LEAD we have now a lot of experiments also for example we don't have experience in the real reactor operation except these submarines which is very limited and actually not available also to for general but however the LEAD was chosen because of the disadvantages of sodiums obviously it's violent chemical reaction with water and can happens and also in case of monju it was a leakage of sodium not many by the way but because of fire and frankly the main problem with leakage of the sodium in monju was because it was JNC was trying to hide this accident from the public and then they lost public support and acceptance and that was because actually such kind of leakage happens with sodium and they are not very dangerous unless you get direct contact with water, with air it's a fire but it's a small fire it's very small fire like which can be easily managed but the problem is that it was a leakage they didn't know and they tried to hide that was a problem we thought we have million experiments also with LEAD also a lot of experiments now and we don't expect the problem with LEAD which is and this is much easier of course and how to replace and why the generation 4 of course I agree with you with the gas for example helium or supercritical water is also high pressure also and also but with traditional PF bar you have one problem it's high pressure reactor and it's potentially has or even with new and new safety measures with everything potentially physically can be dangerous can lead to that dangerous accident in case of several in this case that why this ambient pressure reactors like sodium and lead for example I consider it as generation 4 if I may add something Vladimir to that what you said wait a moment wait a moment let's give a discussion sorry for example for PWR for a thermohydraulic we have more than 140 experimental test data about just for thermohydraulic we have a various design of the generation 4 generation 4 reactors but lack of the experimental it's very big challenges with this variety and as a researcher and nuclear engineering when anyone ask about the future of the generation 4 it's very big issue we need to concentrate more about the technologies and the best technologies for replacement thank you thank you for your comment now Mr. Batra please I was just adding to that I think the prime reason to move to generation 4 is actually outlined in the 4 goals that generation 4 represents which are safety, sustainability, economics and proliferation resistance so if we talk about these 4 goals first let's talk about sustainability we have to see how we can maintain the current fuel cycle we can assume that the current uranium resources are enough but they might not be enough if you want to continue this cycle for a longer time and in terms of safety also one of the key points that Vladimir mentioned is the most of systems are pressurized the pressurized water reactor or boiling water reactor and they itself create a lot of complications in terms of safety so when we depressurize the system it eventually leads to a lot of it eventually eliminates a lot of accidents in the pressurized system now talking specifically on the experimental facility what I think and what I believe in is that the nuclear industry has a very strong regulatory process so if the regulation regulatory process, if the reactor design goes through the regulatory process that means there has been enough evidence that the reactor will operate safely and will not cause any harm to the ambience and with this what I feel is that if there is not enough either physics proof or enough experimental proof the reactor will not be licensed and that we can for sure rely on nuclear industry this has never happened before this is not gonna happen later as well now specifically issues of safety which comes with sodium like sodium fire for me I believe it's not a very big issue because the sodium fire is manageable and these are engineering solutions that we can have for that so in case we have an engineering solution we can move ahead if we do not believe in engineering what's gonna happen is that we had boilers which were blasting every day and now we have boilers in our homes we just rarely or they just never blast because the engineering solutions are there which keep them safe so the whole idea what I feel here is that to move towards a technology which has more sustainability goals and more safety goals but the process takes time and for that I think there are enough experimentation that is happening the industry has enough regulatory process that makes sure this is gonna happen and then the important thing is economics so if the reactors cannot compete on cost with other sources of energy this is the death of nuclear so we have to make sure the economics is good and for that I feel that the generation 4 reactors would actually work on improving the economics of the reactor that's all from us thank you we can continue can you hear me can you everybody we can continue this just quick introduction very small introduction all details we will receive later in our lectures on different types of reactors and you can ask questions also any other questions here it was shown that BN600 or 800 any of them has like lower power density and my question is how much lower it is and is it lower than the regular PW reactor I mean we know that ACFR which is much more higher power density than PWs why was it said that it is lower lower because lower traditionally the first reactors like BN600 for example they had much higher power density than water reactors and PFWR and the core was very small like 1 meter and several 3 meters diameter and that was considered as a benefit but then it becomes theoretically yes you want to have a release you have smaller core and release more energy in the smaller core yes but from the safety point it was to now that it would be better to have lower density so means bigger core with the same power and that was a lower power density for BN200 it will be even more lower this was the safety reason also but it's still higher than PPPWR yes this is intentional because it was considered as a benefit from the very beginning but then it turned out that it could be why should we make all power in the very small ok we can afford a little bit more because it doesn't require more structural materials it's still the reactor vessel is the same size so any other questions from the online audience if you want to raise your hand please no then I think we should go because we are already ahead like half an hour loss because you take very long coffee break guys now I'd like to ask Mr. Chirayobatra to deliver to start his presentation on small and medium sized or modular reactors Hello everybody can you see my presentation? Right?