 A lot focused on the back end of the fuel cycle, so I think it's good that the next presentation from Emparo is on radioactive waste management and decommissioning. So, thank you so much. So, first of all, I would like to show you the reference of the report on repossessed uranium, we mentioned. So, if you Google EIA repossessed uranium, you can find this nuclear energy series, but you can type the reference is number NFT4.4, and this is the report. So, this is my second talk, and I would like to mention that it's not in my section. So, there is another section dedicated to waste technology and decommissioning, and I've been asked by our director to give this talk. So, the first part, it's on radioactive, so the talk is divided into parts. One is dedicated to radioactive waste management, and the second part to decommissioning. The first part is courtesy of the section head of the waste technology section that provide me with information, and I try to do my best to give you the talk and also to answer the questions, and if not, I will address the questions to him. And then I'm sure he will answer properly. So, the content of the talk is, first of all, what means radioactive waste, the definition, the different sources of generation of the radioactive waste, the classification of the waste, and the different stages during the process of managing the radioactive waste. The waste acceptance criteria, and I will mention some of the international conventions in place so far. So, we have a glossary of safety terminology, and in this glossary you can find it on the internet if you Google IAEA safety glossary, and it was... Oh, thank you. I didn't need to read it. That's okay. And it was issue... In 2016, it was the last revision. So, there is mention that waste is any material for which no further use is foreseen. So, in the case of radioactive waste is a waste that contains or is contaminated because it's different. When it contains it's because it's activated and the reactivity is part of the material itself. And when it's contaminated, sometimes the contamination can be avoided, but we can clean the material. Sometimes it's not that easy. But if it's contaminated, we can be contaminated, but if the reactivity is part of the material, we cannot contaminate it. So, the radioactive waste is any material that contains or is contaminated with radionuclides at a certain level of concentration that is below the limit set by the regulatory body for which no other use is foreseen. So, there are many different type of facilities generating radioactive waste, and the waste are completely different. So, it ranges from the radiaisotopes using medical treatments that are very short-lived, and the concentrations are very small, and it ranges from then to our natural occurrence material to the spent fuel. So, the varieties and the forms are huge. And also the facilities can be a small laboratory dedicated to research, produce or generate waste, and the main generator is the operation of the nuclear power plant. So, the range of facilities producing waste is enormous. So, for that, the nature of the waste are very different, and we can find radioactive waste with radionuclides in different concentrations in physical and chemical forms. The radioactive waste can be gaseous, liquid, and solids. And these differences results in a wide variety of options for managing the radioactive waste. So, the main, the overall objective in safety is the radioactive waste should be managed in the form that the risks to people and the environment are minimized. And it should be done in all countries using nuclear technologies. So, for example, to give you an idea of the quantity of the radioactive waste produced by a nuclear power plant around 1,000 megabatts, generate around 200, 350 cubic meters of low level waste and intermediate level waste in the operation of the nuclear power plant, and also generate about 27 tons of spent fuel. And if this spent fuel undergoes to reprocessing, it's generated around three cubic meters of high level waste per year. So, as we see, the radioactive waste are from different, the different nature and from different generation. So, it should be classified in order to harmonize, to compare from one facility to another facility in the same country and also between countries. So, the radioactive waste can be classified according with their physical, chemical, and radiological properties. And due to the difficulties in comparison between facilities and between countries, it was decided to make guidelines for international classification. So, this is the current classification in place so far and the first one was issued in 1970 and it was revised in 1981 and 94 and the last one was published in 2009. So, the INC recommends countries to use this classification in order to harmonize and to be able to compare the radioactive waste produced in one country to another country. And it's very important that we will see at the end of the presentation in terms of the joint convention on the safety of spent fuel and radioactive waste management. So, the convention is a legal banding convention and it's based on the peer review between among countries on what they are managing. So, the classification should be comparable, otherwise we don't know if we are, when we are talking about intermediate level waste, what does it mean, or low level waste, what does it mean in one country to another country, should mean the same in all countries in order to compare and to be able to talk about it. So, this is the current classification proposed by the INC and included in the document I mentioned before. So, first of all, we have the exempt waste. What does it mean? It's the waste that the content, the radioactive content doesn't reach the level set by the regulatory body. So, it can be cleared or exempt to go under regulation. The second category is the very, and this is very important in the commissioning, for example, because in the nuclear power plant, if we consider everything because the nuclear power plant is a nuclear facility itself, if we consider everything under regulatory constraint, there is a huge amount of waste and there are a lot of buildings that are not contaminated and never were exposed to contamination. So, they can be cleared and they can be apart from the regulation. So, they are measured and they are exempt waste. They are considered not contaminated and they are not undergoes to the managing of the radioactive waste material. So, we have another. The second category is the very short-lived waste and it's mainly those material used for medical purposes because the health life of the radioactive waste used are very, very short hours or days, but not longer than that. So, this activity, this waste can be managed, only keep it in some store facilities in the same facility of the producer and leave it them until decay. And when it decay, it can be managed as conventional waste. And, for example, some medical waste produced by radiofarmac are more dangerous by the biological risks. For example, the needles are more risked by the biological risk than the radiological. So, radiological, if we can, if we leave the waste for months or years, they are sure that their activity has decay under the limit and it's no longer a risk and they are then treated as biological waste. So, the third category is the very low-level waste and they don't need a high level of containment or isolation and they can be disposed in the surface, in the repository surface and we will see the different options. Then the fourth category is the low-level waste and so they have levels above the clearance and they have limited amounts of long-lived radionuclides that usually are alpha emitters. So, for example, in the case of Spain, it's the case of El Cabril. I don't know if you've heard about it. Let's talk about it. So, if our repository in the southwest of the country and it's dedicated to low-level and intermediate-level waste, but they are very strict in the alpha emitters that can be disposed of there. So, this is the limitation because they consider them low-level waste. And we have another category. The fifth category is the intermediate-level waste and so they have... they content a certain amount of long-lived radionuclides that can be beta-gam emitters and alpha emitters. They require greater degree of containment and isolation and they are disposed underground, a few meters underground. And the sixth category is the high-level waste that consists in the spent fuel itself when it's considered as a waste in the open cycle option or the high-level waste produced after reprocessing of the spent fuel after the PUDEX process and it's mainly formed by fission products and myelactinites. And they are vitified in glasses matrix, conditioned in glasses matrix and disposed in deep geological repository as a spent fuel. So, for example, to give an example of an activity that generates low-level, intermediate-level and high-level waste is the reprocessing activities. So, once uranium and plutonium is reprocessed and recycled products, they generate waste and the waste are the residues. So, the residues are originated from the irradiation of the fuel and the reactor and they are the hues and the end fittings of the tubes of the rocks containing the fuel and also residues are the myelactinized and the fission products that form the high-level waste stream that has to be vitified. So, the hues and the end fittings are considered intermediate-level waste and they are super compacted and we will see later. And the myelactinized and fission products are high-level liquid waste that has to be solidified including in a condition in a matrix glass. And there are the so-called operational waste that are generated in the operation of the facility. So, they are low-level and very low-level waste and also they are intermediate waste. High-level is the myelactinized and fission products but there are, for example, some resins originated in the purification processes that have to be managed as radioactive waste. And I don't know if you can see it properly. So, this is the conceptual classification that you can find in the safety guide I mentioned. And so it gives an idea, this is the level of activity and this is the time frame. So, you see the six categories are drawn in this draft. So, this is the exemption waste. This is the short-lived that decay very, very fast. This is the low-level waste, the intermediate waste and the high-level waste that needs a lot of time to reach the low-level or the exemption level. And in terms of safety, a radionuclide with a half-life lower than 30 years is considered short-lived. So, all radionuclides with a half-life higher than 30 years are considered long-lived radionuclides. So, the different stages include in the management of the radioactive waste are the basic steps are drawn in the picture and it's considered in the pre-treatment treatment and then it's when the waste are segregated in those who can be considered not radioactive waste anymore and conventional waste and those and the materials that can be recycling inside the nuclear cycle. And then once the waste are treated, are conditioned to make them solid and difficult the radioactivity to be unleashed and released and then after a period of storage they should be disposed of or directly from conditioning they can be disposed of. Sometimes they don't need to pass through the storage. This is a very genetic draw. So, this is in the case of high-level waste of a spent fuel but some of the low-level waste or intermediate waste can be conditioned and then directly disposed of in the suitable facility. So, let's talk about the waste pre-treatment. So, the main objectives of this stage in the management of the radioactive waste is to segregate the material into active and non-active so we can exempt some of the materials and also to separate them in different stream components and this is very important because when the facility received the waste or produced the waste they are of different level of contamination different level of activity content. So, and sometimes we can produce cross-contamination so it's very interesting to keep all streams separately to avoid cross-cutting contamination and to produce huge amount of waste. So, the first principle is to produce as low volume as possible of radioactive waste. So, another objective is to convert the waste into a form that it's easily to be treated and conditioned and to recover products for recycling. So, if we segregate from the beginning it's easier to recycle some of the materials that we put everything together and then we segregate it. Sometimes they are contaminated and they are not easy to recycle after. So, the most important part of this pretreatment is the decontamination activities that the main objective is to reuse the materials to able to reuse the material and to reduce the contamination and sometimes if the contamination can be avoided the classification of the waste can be lowered from intermediate to low level that make it easier to manage the radioactive waste. Also minimize the personnel and the workers' exposure and allows the product recovery and always we have to keep in mind the benefits and the drawbacks of decontamination because sometimes we have something contaminated in 1 cm, cubic cm and it's very easy to manage because the volume is very low and then if we try to decontaminate it we create liters and liters of contaminated water or contaminated organic solvent sometimes it's much difficult to manage. So, the balance between the benefits economic and also from technical point of view should be always keep in mind and the characterization. So, the characterization of the radioactive waste is very important in all stages of the management of the radioactive waste because first of all, we have to know what is included, which type of contamination or which type of radionuclides are contained in the waste also it's important to have the inventory of the radionuclides stored or disposed in the facility. So, for example, in the case of a facility dedicated to low level very limited to low level radionuclides it's necessary to know the inventory because the regulatory body never allows or the facility is not licensed for low level radionuclides the level of alpha emitters should be keep under a certain level so the characterization is very important and it's not easy to characterize the radioactive waste because the gamma emitters can be characterized with non-destructive methods because the gamma rays are difficult to stop so with a detector, a germanium detector we can easily detect but what's happened with the content of alpha emitters beta gamma emitters, pure beta emitters as strontium 19 or uranium plutonium that's only made gamma rays so they are very difficult to characterize and it's necessary to develop methodologies that using destructive methods can allow the facilities to get the inventory and then to apply the so-called correlation factors so measuring the gamma emitters can calculate knowing from where the stream comes the alpha and beta content so it's not an easy task to characterize and it's very important and it's also necessary to meet and to be sure that the waste meet the acceptance criteria so the most common definition of the waste acceptance criteria and it could be applied also to spend fuel sorry are those requirements that are to be met by conditioned radioactive waste forming packages to be accepted at an interim storage or at a disposal facility but it's not only important at the final for the interim storage or disposal facility it's also the waste acceptance criteria are also very important in all different stages of the management because for example if we produce a material in the case of a spent fuel if we storage the fuel in or we manage the fuel in a certain circumstances we have to be and we have to keep in mind what is the next step because sometimes decision-staking in one stages have a lot of impact in the second stage so now the approach for radioactive waste and also for spent fuel management is to have an integrated approach to the whole management and then we are sure that the decision-staking in one stage doesn't have a lot of impact in the next stages of the process this is the issue from the beginning that's why we are working now into an integrated approach of the different stages it's very difficult to have in mind now what will happen in 60 years because for example in the case of radioactive waste you know what the disposal facility the requirements for the disposal facility are you know so you have to have in mind in all the process they accept the criteria at the end and for the radioactive waste in the immediate low level it's not that difficult because the facilities are now in place but for spent fuel storage for spent fuel disposal for example it's very difficult to have in mind so now we have a meeting a big meeting it was a conference in 2015 and the main message of the conference on spent fuel management was we should approach the management of spent fuel in an integrated way and the communities has to talk to each other because the community dedicated to storage doesn't have in mind disposal issues even in the agency for example we are separated in different sections so we are working in the storage in one section and they are working in the disposal in another section and we have to talk to each other and we have to be aware what the needs in disposal and disposal have to have in mind what is happening in storage so far to be able to smooth the interfaces so there's a lot of effort applied to that because it's very difficult so in the ideal world we should have some acceptance criteria that of course the technology changes and maybe solutions in 60 years are completely different that we know now but at least we should have something in mind for disposal and it should be known by the people working now in the storage to keep in mind that in the future the constraints or the needs will be this and that and that and it's not that easy even for example for the safeguards if I explain like this it sounds very funny and it's not funny so we have a meeting in April in the agency with the main actors in the world on disposal and storage and then we invite a person from safeguards and the person from safeguards said now we are working so hard very hard with countries for example from Sweden and the representative from Sweden said ah thank you because they designed the facility for disposal without taking into account the safeguards requirements and then the lady from safeguards said and we need inspection here inspection there, inspection there and then once the walls are built then we have to drill oh no so it sounds common sense but the communities are very isolated and a lot of effort now is applying to have in mind all the requirements in the disposal or in the storage but mainly in the disposal because it will last a lot of time so it's not that very difficult and of course this is the general definition and as the waste are more difficult to manage the acceptance criteria are more difficult to meet at the end so what are the results of the pretreatment so we will try to improve the safety to lower the radiation exposure and so we have to balance the effort and benefit not to avoid generating a lot of secondary waste that sometimes are more difficult to manage than the primary waste treatment so there are different operations in treatment that in principle are dedicated to reduce the volume and to remove when it's possible the activity of the waste to lower, placidicate them and we have some examples of liquid waste treatment and as you can see they are dedicated to reduce the volume so after filtering or evaporation, distillation or ion change resistance purification we can have a reduced volume of waste and in order to condition a lower volume but sometimes it's more difficult so we have to keep in mind that sometimes the conditioning of the concentrators are more difficult than the conditioning of the waste itself so an important consideration to choose the treatment for the liquids the characteristics of the waste and sometimes for example if we separate the liquid sorry, the liquid stream by distillation we can have water and the concentrate and the water we can discharge because by distillation we cannot have contamination in the distilled liquid and in the case of solid waste there are different methods based on compactation and also melting or incineration and chemical and biochemical treatments so for example in the case of compaction sometimes we can compact inside the drum this is the normal harmonized 220 liters drum and a lot of volume of waste are produced in the operation so there are the gloves, the cover shoes the clothes, the masks and these waste can be compacted to increase the volume that can be placed in one drum or sometimes with the metal parts as we saw during the processing with the hues for example of the rods we can super compact these waste to reduce a lot the volume so you can see here in the slide the volume reduction when we compact in the drum is two or five times and super compaction the reduction is 10-15 times and then we improve the volume in the repository other option is the incineration and it's a normal like in the conventional waste so the organic part is transforming CO2, water and we get a secondary waste the ashes and the volume is reduced dramatically so we have volume reduction 50-100 times and melting is used during the commissioning for example some research reactors the aluminum part of the core can be melt and the products are separated in the result metal and also what it means in English, I don't remember the name, slag slag so has been proved that the main radioactive content remain in the slag while the metal remains clean and can be recycled inside the nuclear cycle so the off gas so the off gas are treated with filters with EPA filters or also some gases are trapped in absorption beds yes depending on the contamination you can incinerate the filters if they are made of incinerable material you can incinerate the filters and then get the ashes and manage the ashes but yes, of course sometimes it depends on the size of the filters the humidity in the case of the filters the filters are mainly so I'm not especially in the off gas treatment but I think there are different traps, different levels the water condensate at less than 100 degrees so you can have lower condensation of water and then the EPA filters avoiding to have water you know what I mean so you have a cool tower and then the emanations are cooled before to get the filter that are sensitive to humidity so you can walk like this I get so because there are different steps in the filtration so of course the off gas has to be treated in the case of the reprocessing facility where the spent fuel is shopped and solved the main radionuclides of gases contained in the spent fuel is the iodine and the noble gases that usually are inside the pellet or in the places between the pellet and the clad and should be these gases are treated by appropriated filters so conditioning the main idea is to solidify the waste and to put the waste in the form that the projectivity will be difficult to be leached and to be released so in the case of low level and intermediate level the cement is the more used matrix and in the case of high level waste is the glass matrix there are different packages so once the suitable matrix is identified it mixes the matrix with the waste and then is solidified and immobilized in a package so this is a 220 liters drum and this is for example concrete packages for more active waste because concrete stops the chemical emissions and these isocontainers are mainly used in the commissioning for sands for big volumes of radioactive waste with very low contamination and they are put like this because there is design characterization procedure with three and three detectors so the box the isocontainers pass through the six detectors and in a slow speed and then is detected if the content is below the certain levels and then it's considered a cement or they are considered radioactive waste and there is a harmonized procedure to characterize this type of containers you mean the external corrosion or the internal corrosion yeah as far as I know so far the concrete is improved to keep it safe because for example some facilities dedicated to low level are based on concrete as immobilized matrix also as structural containment and as the buildings of course the concrete has to meet some specifications and requirements to be used in the radioactive waste facility as a matrix or as a structural containment and the facilities are licensed by 300 years and it's proved that it's licensed by it's time so it's like the buildings it's considered a suitable material for example in the case we will see later in the case of some facilities at least in Spain El Cabril is based on a concrete structure as a matrix and also different cells plenty of trumps and immobilized with concrete so after the conditioning the waste has to be stored I think we talk a lot about storage and then has to be disposed of and this is the options so for very low level waste can be stored in the surface for low level waste needs to be stored underground but not very deep only few meters deep for intermediate level waste they need more isolation so they have to be disposed in deeper constructions for high level waste or spent fuel is a deep geological repository sorry I think in any case but it's more important in the case of intermediate and high level waste but in any case because if you put surface repository in a seismic area it's not good but it's not a risk high risk but in the case of intermediate or high level waste is one of the main parameters to be taken into consideration the same requirement I don't know because I'm not safety specialist so maybe you should ask somebody from safety for license I don't know by my common sense it should be the same but I'm not sure but for example in the case of geological repository because the nuclear power plant is licensed for 40 years of lifetime but in the case of the geological repository it will last for a long time so maybe it shouldn't be the same maybe it should be more restrict in this case but I don't know so yeah because the nuclear industry is always very very very safe but maybe it's much more in the case of the geological repository I don't know yeah yeah in principle it's mainly dedicated to the source sources yeah but the source sources is a radioactive waste also I think so far the current options are dedicated to the source sources I guess more than intermediate but in this slide it's considered all radioactive waste not only those came in from the nuclear power plant so this is a graph facing the different options with the different levels of classification of the radioactive waste so we see the very low shortleaf and very low surface low level some meters below or over the ground and intermediate deep and high level waste very deep so this is an example of engineers near surface fossil concepts and for example you can see here the concrete structure the cells are made of concrete and the idea is to fill these cells anything is the same like here with drums in a square cells filled with concrete and then fill all these cells with concrete and cover them and at the end the remediation is made with vegetation I don't think so I don't think the formulation of the concrete to be put in as a matrix it's it's a spatial facility for low level waste and the concrete is used as a matrix to immobilize the low level waste and the formulation of the concrete I think is licensed to last the whole period and to avoid the leaching of the radioactive and it's used as a matrix it's a conventional matrix for low level waste and the other option is when it's few meters below the ground floor is the trench type disposal and you can see different examples in the United States in France in Argentina for example and it's dedicated to low level waste so far the low level waste disposal is mature and well understood practice and the requirements are you can find the requirements in this safety guide SSR 5 about the disposal of the radioactive waste and so there are more than 100 low level waste repositories working so far in the world so there is a lot of lessons learned and operation experience gathered and this there are different range of disposal solutions and since there are different types of radioactive waste produced in the different operations with the applications of the nuclear energy and this these experience gather are very useful for the newcomer countries of the countries we started working with the applications of nuclear energy not only with the nuclear energy production so the INC is always fostering the sharing of lessons learned and the operational experiences and this is options for the mine cavities is when the intermediate level waste are disposed of deeper and below the ground and these are the examples of the different options of the geologic repository and we talk about them during the last talk so the option for high level waste as we mentioned is the deep geological repository and the most important thing is now after experiences there is a clear recognition that the importance of the stakeholder engagement and now there is a lot of effort put in engage and find the ways to engage the stakeholder from the beginning of the disposal facility and the decision and the siting process so we talk about this I'm not going to repeat that and one of the most important things to minimize the waste the volume and also the radioactive content and it's made using the generation at source and recycling and reusing the material and it should be made in all the stages of the nuclear energy cycle so since the facility designed through the operation and during the decommissioning of the nuclear power plant so as I mentioned there is a lot of effort now put in the stakeholder involvement and there are a lot of activities performed by the INC and also in collaboration with other international organizations as the OECD NEA and the European Commission because it's important to build trust and confidence of the public in the nuclear industry and the nuclear applications because many people go to the hospital and they don't know that they are treated by nuclear material and they don't know so I think there is a lack of communication to the public about the benefits and what they are receiving from the nuclear applications and the nuclear industry so let's talk about the international conventions so since the countries are not working now isolated so there is a lot of international relations and there is a directive issued by the EURATOM in the European Commission in 2011 about giving a guide and advice to the countries on how to manage radioactive waste and spend fuel to harmonize the practices and also there is a code of conduct on the safety and security of the reactive sources and now there is the joint convention on the safety of spend fuel management and radioactive waste management and I'm going to talk a little bit about it and the joint convention is a legally binding agreement between contracting parties so the countries are free to sign the contract but the INC is fostering and trying to encourage the countries to sign the contract and to be part of the joint convention is the only international legally binding instrument in the area of safety and security of spend fuel and radioactive waste management and it's based on the safety fundamentals of radioactive waste management so this is the story in 1997 the board of governors authorized the DG to convene a diplomatic conference and in September of this year the joint convention was signed by 42 member states and entered into force in 2001 so every three years there is a meeting that was in May 2015 and the next one will be in May 2018 so next year and so far there are 76 contracting parties as July 2017 so what is the objective of the joint convention is to achieve and maintain high level of safety worldwide and to ensure that there are effective defences against potential hazards to the individuals and to the environment and also the idea is to prevent accidents and mitigate their consequences so when countries sign as contracting parties they commit to adopt the appropriate measures to ensure the safety of spend fuel and radioactive waste management they commit to prepare and submit a national report for the peer review of the other contracting parties they commit to responding within to the questions addressed and submitted by other contracting parties to attend the meetings every three years and also to commit to participate actively in the review process so this is a strategy of every contracting parties a peer review by the other contracting parties so in this case the INC only act as a secretariat so we are the depository we are in charge to organize the meetings to hold the meetings to maintain the website with the information and also to make promotional activities to promote and to make other countries to sign as contracting parties and for example the last two years we got six new so we were 70 contracting parties by 2015 and now we are 76 so in two years we got six more contracting parties and the joint convention belongs to the countries themselves so they have to submit a national report that shall contain the policy and practices for spend fuel and radioactive waste management to address the criteria to categorize the radioactive waste and they have to include the listing of facilities and the inventory of spend fuel and radioactive waste and they have a web page you can find in this link and they decided which information they would like to make public to the public or they keep resale by themselves so I think I'm going to go quickly to the decommissioning part so only as a conclusion if the radioactive waste are managed safely securely and environmentally we would like to have more public confidence in the nuclear industry that increase the acceptability of the nuclear energy and the nuclear applications so now let's move to the decommissioning part of the talk I will try to be as fast as I can so this presentation is a courtesy of my colleague who is a technical leader of decommissioning in the waste technology section and environmental remediation so looking to the safety glossary nuclear decommissioning is the administrative and technical actions some or all of the regulatory controls from a facility but not only from a facility because there may be areas of land that have become contaminated during operation of a facility and the cleanup of these areas is also part of the decommissioning so the commissioning activities have to be performed with a progressive and systematic reduction of the radiological hazard and it's undertaken on the basis of a very rigorous planning and assessment to ensure safety, protection of workers and the public and the environment as well and it should be taken into consideration as a normal and expected part of the life cycle of any industrial facility so as we will see that the commissioning should be keeping in mind from the beginning of the design of the facility because if we have to dismantling a facility and it was taken into account at the time of the design it should be easy so this is the current situation so there are more than 19 power reactors the commission so far and there are more than 400 other facilities including research reactors or research and development facilities universities and nuclear fuel cycle facilities that have been shut down for decommissioning and undergoing decommissioning so there's a lot of knowledge and experience on the commission so far so these are some numbers that you can get if you type priest is the INC power reactor if information system thank you and if you type Google EIA priest you can get the link and also we have a database on reactor and nuclear fuel cycle information system also for nuclear fuel cycle facilities and you can find this type of numbers of the nuclear reactors in operation which are long-interpreting shutdown or impermanent shutdowns and so on this is the outlook of decommissioning of the power plants and so it's foreseen growing in the decommissioning of the power reactors and this is the scenario for the shutdown so in 2020 something most of the plants that were built and constructed in the 80s will reach the end of the life and they will go under decommissioning so as it's mentioned in the general safety requirements on decommissioning of facilities you can find these three decommissioning strategies one is the immediate dismantling it means that decommissioning actions begin shortly after the permanent shutdown and everything is removed and the land is clear for other purposes but there is another option that is deferred dismantling and when it's considered that after shutdown the country wait or the operator wait until 40-60 years starting the dismantling of the facility in this case they use this time to allow the short lived life to decay and then the productivity to be managed is lower and the decay heat is lower so the strategy that the country can choose but in the case of the deferred dismantling since they wait 40-60 years there could be a lot of changes in the requirements and in the safety and in the governments so it's very dangerous and the cost maybe can cost a higher cost at the end and the third option is the so-called entopment and it's a combination of the two other options so on one hand some parts of the facilities and the commission and another part are kept in safe mode so are conditioned in order to avoid the reactivity release but this option is not considered as the commissioning strategy and it's not an option in a normal shutdown it's only considered in the case of normal circumstances as a severe accident or as we will see in the case of the reactors using graphite it has decided to go through this option and I will explain later so these are some numbers of the plants so far so there are around 50 that go or plants to go under deferred dismantling there are around another 50 that plans to go under immediate dismantling and there is these three entombed so the radioactive material has been conditioned in C2 so the land has to be restricted access and restricted use and there are around 25 without any decision taken so far so this is for example this is an example of one nuclear power plant under immediate dismantling so it is the Yankee Row nuclear power plant in the United States and it was fully dismantled in 2007 and the shutdown was in 1992 and you can see the land with the nuclear power plant the land after with the completely commission the commission site but the spent fuel remain in the site so now it's a problem that for example in the case of the United States most of the plants are reaching the end of the lifetime or they are shutting down due to economic reasons and the storage remain on site and at the time the nuclear power plant is in operation it's fully stuffed but should be remain stuffed that take care about the storage facility so it's an issue that now countries are facing how to deal with different inter-emerge storage sprout all over the countries and also in Spain we have the same problems we are building inter-emerge storage because we don't have any centralized inter-emerge solution we are building inter-emerge storage in three, four of our nuclear power plants and at the end of the lifetime when the nuclear power plant will be the commission the storage will remain alone there and it's an example of deferred dismantling so it's an example of the nuclear power plant of graphite gas it was Bandaios one it was shut down in 89 after an accident without any environmental consequences but the operator decided to shut down the plant and so this was the plant and then after the demolition and dismantling the graphite is kept so the spent fuel was sent to France for reprocessing but the graphite is very difficult to manage and was kept for a dormancy period of 25 years that will be finished in 2028 yes because it was started in 24 for 25 years to allow the the majority of the activity to decay because the graphite the radionuclear inventory of the radiative graphite is unusual in comparison with another nuclear waste so there is a lot of cobalt 16 that has a half life of 5 years and there is a tritium a huge amount of tritium and it's one order of magnitude of the concentration of carbon 40 and it's also chlorine 36 that is a long term because it's already a nuclear emitter with a long half life so now there is a project run by the INC in order to harmonize and to find solutions among all countries that have nuclear power plants with radiative graphite to gather practices and to discuss and to find harmonized solutions among countries to manage the radiative graphite so the decommissioning has to go under a very strict plan so the successful decommissioning depends on the careful organized plan and should be prepared for any nuclear facility so the INC recommends to prepare the plan for decommissioning at the beginning before the operation of the facility and to revise the plan so in that case the records of the all changes that during the lifetime of the facility are made should be kept as a record and facilitate the decommissioning tasks and also the INC recommends when a nuclear power plant is shut down to start the operation taking the spent fuel to store on site or away from the reactor but starting discharging the spent fuel from the core from the first part so the responsibilities associated with the decommissioning we have three main bodies the government, the regulatory body and the licensing so the government is to establish a national policy for the management of the radioactive waste and also the waste generated during the decommissioning the government is responsible to establish and to maintain the legal, so with the regulatory body and the technical and the financial responsibilities for organizations involved in the decommissioning so the government is responsible to be sure that there will be funds available at the time of the decommissioning of the nuclear power plants and also they are responsible to ensure that there are the necessary scientific and technical expertise in the country to do the decommissioning activities the regulatory body shall regulate all aspects of the decommissioning throughout all stages of the facility's lifetime and during the decommissioning so it's the responsible to issue the license for operation and also the license for decommissioning and the licensing shall plan for decommissioning and shall conduct the decommissioning actions in compliance with the authorization of the decommissioning issued by the regulatory body and is the responsible for all aspects of safety, radiation protection for the workers and for the environment so what are the decommissioning challenges so the first one is the financial needs so as you can see I put some figures of the cost of decommissioning of different plants in Spain it's very small plant and also in Finland and in Slovak and this is the forcing cost so there is also a needs or research and development and innovations in technologies for characterization and survey for segmentation and dismantling and the contamination and remediation of the environment means there are different types of facilities to be dismantled the INC is organizing discussion groups to share information and to put in common all the developments the different countries are getting so it's the country estimation for the cost because they consider all the implications because they love each other in Finland and they have the disposal facility available and I don't have all the considerations they consider when they calculate the cost this is the calculated cost by every country but it's to give an idea that it's about 100 million of euros and I guess this is the initial calculation and the final calculation is completely different and the final cost will be completely different so this is the estimation cost depending on what is considered so at the end we finalize the same as during the nuclear spend fuel and radioactive waste management so it's necessary to have effective stakeholder involvement also in the commissioning and environmental remediation activities because there is a huge amount of waste managed during these activities so and this is very important because there is a lot of international cooperation and collaboration in this field so as an example the INC NEA and the European Commission are working together and for example the OECD launched in 1985 a program dedicated to exchange scientific and technical information and they are still working in this project so the phase will start in 2014 in 2018 the last phase of this project and after Fukushima accident in 2013 Japan established the IRIIT project and it's the International Research Institute for Nuclear Decommissioning and in January the INC also after Fukushima accident in January 2015 established the DAROT project as is the project on decommissioning and remediation of damaged nuclear facilities under the INC nuclear safety action plan under the INC nuclear safety action plan and the project gathered 35 international experts from 19 member states so you have here the links of the three webpages with you can find the information of this international collaboration so what is the INC doing in the decommissioning program so we are developing technical publication and safety guides as you see the network we have an international decommissioning network we collaborate with the technical cooperation department projects on decommissioning to help member states we held some conferences and the last one was the international conference in Spain in May 2016 we also organized peer reviews missions to review the national decommissioning programs and you can find a lot of information in the decommissioning module in the PREIS information system so these are some publications and this is the conference here in Madrid and this is the link you can have all the information for the conference in this link and some examples of activities related to decommissioning we have a wiki under the network on the commissioning and so the wiki can be used for a number of purposes such as helping to select the basis mantling or the contamination methods or identifying where different decommissioning activities are taking place opportunity for benchmarking so you can join the network and then you can have access to this wiki to get the information and you can here you can find the links to get the access and this is the different networks we have in the INC so once you have the nucleus access you can request access to the decommissioning network also to this POSAL network or the spend fuel management network sorry for the time I get and we are also developing ill-earning material and they are publicly available those in green are already available and the web page of the INC is public but it's not that easy to find so you need to search and search and search and then you get the material so it's publicly available but it's difficult and this is the link so there are some modules on this POSAL and remediation already published and now we are working to develop a module on spend fuel management so this is the platform where you can get the illearning material and it's very interesting I recommend you to look at this material and that's it, thank you for your attention