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The first license application for the third unit was made in December [28] and the date of the unit's entry into service was estimated to be In July TVO announced that the unit would not go into service before , [14] [29] five years after the original estimate. In a statement, the operator said it was "not pleased with the situation" although solutions to various problems were being found and work was "progressing", and that it was waiting for a new launch date from Areva and Siemens.
According to Kauppalehti , the estimated opening was delayed until — The delay was caused by slower than expected modification works. The delays have been due to various problems with planning, supervision, and workmanship, [14] and have been the subject of an inquiry by STUK , the Finnish nuclear safety regulator.
Later, it was found that subcontractors had provided heavy forgings that were not up to project standards and which had to be re-cast. An apparent problem constructing the reactor's unique double-containment structure also caused delays, as the welders had not been given proper instructions. In , Petteri Tiippana, the director of STUK's nuclear power plant division, told the BBC that it was difficult to deliver nuclear power plant projects on schedule because builders were not used to working to the exacting standards required on nuclear construction sites, since so few new reactors had been built in recent years.
Construction of the turbine succeeded better under the responsibility of Siemens. Installations of the main turbine equipment were completed about one year behind the original schedule. However, as of , the construction of the EPR in France is ten years behind schedule. OL3 is expected to produce an additional 12,, GWh annually.
In , professor Stephen Thomas wrote, "Olkiluoto has become an example of all that can go wrong in economic terms with new reactors," and that Areva and the TVO "are in bitter dispute over who will bear the cost overruns and there is a real risk now that the utility will default.
The delays and cost overruns have had knock-on effects in other countries. The construction workforce includes about 3, employees from companies. In it was reported that one Bulgarian contracting firm is owned by the mafia, and that Bulgarian workers have been required to pay weekly protection fees to the mafia , wages have been unpaid, employees have been told not to join a union and that employers also reneged on social security payments.
The decision was approved by the parliament on 1 July In September , with unit 3 still unfinished, the Finnish government rejected TVO's request for time extension of the unit 4 decision-in-principle. Economic Affairs Minister Jan Vapaavuori referred to the long delay of the 3rd reactor and to unsatisfactory assurances by TVO that the 4th unit would ever be built. Nevertheless PM Stubb stated that the rejection didn't spell the end for the OL4 project, and that TVO would have the opportunity to apply for a construction license before the decision-in-principle expires in June In June TVO decided not to apply for a construction permit for the Olkiluoto 4 unit because of delays with the unit 3, however saying they are prepared to file for a new decision-in-principle later.
The Onkalo spent nuclear fuel repository is a deep geological repository for the final disposal of spent nuclear fuel, the first such repository in the world. It is currently under construction at the Olkiluoto plant by the company Posiva , owned by the nuclear power plant operators Fortum and TVO.
The power plant hosts the northernmost vineyard in the world, a 0. An incident occurred at unit 2 on 10 December at Because of a valve repair work, excessively hot water flowed to the reactor water clean-up system filters.
The hot water dissolved materials from the filters. When the clean-up system was restarted, the dissolved materials flowed to the reactor core, where they became radioactive. This caused the radiation levels in the steam line to rise momentary 3—4 times higher than the normal level. The increase of the radiation level activated safety systems, which operated as planned and triggered reactor scram , closed containment isolation valves, and started the containment spray system.
The operators followed procedures and declared a site area emergency at There was no radioactive release to the environment, and the workers were not exposed to radiation. In April a turbine steam condenser of unit 1 had a small seawater leak, at a rate of two litres per hour. According to the operator, the leak forced to limit the plant output down to MW, but was not serious and was to be repaired in a day.
From Wikipedia, the free encyclopedia. Nuclear power plant in Eurajoki, Finland. Main article: Onkalo spent nuclear fuel repository. Finland portal Energy portal Nuclear technology portal. List of nuclear reactors Finland Hanhikivi Nuclear Power Plant Nuclear engineering Nuclear power in Finland Onkalo spent nuclear fuel repository Into Eternity , a documentary about the construction of a Finnish waste depository Journey to the Safest Place on Earth , a documentary about the urgent need for safe depositories.
Energy Storage News. Archived from the original on 16 June Retrieved 28 August World Nuclear News. Retrieved 17 June Retrieved 2 February Teollisuuden Voima. January Retrieved 16 April International Nuclear Safety Center. Archived from the original on 3 December Retrieved 13 March Nuclear Engineering International.
Archived from the original on 4 September Retrieved 12 January Retrieved 7 January Retrieved 20 September Retrieved 2 July Retrieved 24 July Retrieved 10 August Retrieved 15 April Worldwatch Institute. Archived from the original on 27 September Helsingin Sanomat. Archived from the original on 20 October Power Reactor Information System.
Archived from the original on 19 September Nuclear Street. Retrieved 9 December Retrieved 16 December Retrieved 29 January Archived from the original on 26 February Financial Times. Archived from the original on 1 February Retrieved 18 January Retrieved 27 February Archived from the original on 4 March Retrieved 28 February Retrieved 17 July Power Engineering. Retrieved 23 November Retrieved 29 November Retrieved 13 December The Wall Street Journal.
Retrieved 4 December Retrieved 12 March Retrieved 4 June Retrieved 7 March Physicians for Social Responsibility. They achieve criticality by having a sufficient volume of salt with sufficient fissile material.
Being fast spectrum they can consume much more of the fuel and leave only short lived waste. While most MSR designs being pursued are largely derived from the s Molten-Salt Reactor Experiment MSRE , variants of molten salt technology include the conceptual Dual fluid reactor which is being designed with lead as a cooling medium but molten salt fuel, commonly as the metal chloride e.
Plutonium III chloride , to aid in greater "nuclear waste" closed-fuel cycle capabilities. This latter British design was found to be the most competitive for Small modular reactor development by a British-based consultancy firm Energy Process Development in This reactor concept mixes the liquid natural uranium and molten chloride coolant together in the reactor core, reaching very high temperatures while remaining at atmospheric pressure.
Another notable feature of the MSR is the possibility of a thermal spectrum nuclear waste-burner. Conventionally only fast spectrum reactors have been considered viable for utilization or reduction of the spent nuclear stockpiles. Thermal waste-burning was achieved by replacing a fraction of the uranium in the spent nuclear fuel with thorium.
The net production rate of transuranium element e. The supercritical water reactor SCWR [21] is a reduced moderation water reactor concept that, due to the average speed of the neutrons that would cause the fission events within the fuel being faster than thermal neutrons , it is more accurately termed an epithermal reactor than a thermal reactor.
It uses supercritical water as the working fluid. SCWRs are basically light water reactors LWR operating at higher pressure and temperatures with a direct, once-through heat exchange cycle. As most commonly envisioned, it would operate on a direct cycle, much like a boiling water reactor BWR , but since it uses supercritical water not to be confused with critical mass as the working fluid, it would have only one water phase present, which makes the supercritical heat exchange method more similar to a pressurized water reactor PWR.
Supercritical water-cooled reactors SCWRs are promising advanced nuclear systems because of their high thermal efficiency i.
The main mission of the SCWR is generation of low-cost electricity. It is built upon two proven technologies, LWRs, which are the most commonly deployed power generating reactors in the world, and superheated fossil fuel fired boilers , a large number of which are also in use around the world. The SCWR concept is being investigated by 32 organizations in 13 countries.
Because SCWRs are water reactors they share the steam explosion and radioactive steam release hazards of BWRs and LWRs as well as the need for extremely expensive heavy duty pressure vessels, pipes, valves, and pumps.
These shared problems are inherently more severe for SCWRs due to operation at higher temperatures. A fast reactor directly uses the fast neutrons emitted by fission, without moderation. Unlike thermal neutron reactors, fast neutron reactors can be configured to " burn ", or fission, all actinides , and given enough time, therefore drastically reduce the actinides fraction in spent nuclear fuel produced by the present world fleet of thermal neutron light water reactors , thus closing the nuclear fuel cycle.
Alternatively, if configured differently, they can also breed more actinide fuel than they consume. The gas-cooled fast reactor GFR [21] system features a fast-neutron spectrum and closed fuel cycle for efficient conversion of fertile uranium and management of actinides.
It will use a direct Brayton cycle gas turbine for high thermal efficiency. Several fuel forms are being considered for their potential to operate at very high temperatures and to ensure an excellent retention of fission products: composite ceramic fuel, advanced fuel particles, or ceramic clad elements of actinide compounds.
Core configurations are being considered based on pin- or plate-based fuel assemblies or prismatic blocks. The European Sustainable Nuclear Industrial Initiative provided funding for three Generation IV reactor systems, one of which is a gas-cooled fast reactor, called Allegro , MW t , planned to be built in a central or eastern European country. The largest ever operated was the Superphenix reactor at over MW of electrical output, successfully operating for a number of years in France before being decommissioned in This is considered an important milestone in Indian breeder reactor technology.
After numerous delays, the government reported in March that the reactor might be operational only in December The Gen IV SFR [21] is a project that builds on two existing projects for sodium cooled FBRs, the oxide fueled fast breeder reactor and the metal fueled integral fast reactor. The goals are to increase the efficiency of uranium usage by breeding plutonium and eliminating the need for transuranic isotopes ever to leave the site.
The reactor design uses an unmoderated core running on fast neutrons , designed to allow any transuranic isotope to be consumed and in some cases used as fuel. In addition to the benefits of removing the long half-life transuranics from the waste cycle, the SFR fuel expands when the reactor overheats, and the chain reaction automatically slows down. In this manner, it is passively safe. One SFR reactor concept is cooled by liquid sodium and fueled by a metallic alloy of uranium and plutonium or spent nuclear fuel , the "nuclear waste" of light water reactors.
The SFR fuel is contained in steel cladding with liquid sodium filling in the space between the clad elements which make up the fuel assembly.
One of the design challenges of an SFR is the risks of handling sodium, which reacts explosively if it comes into contact with water. However, the use of liquid metal instead of water as coolant allows the system to work at atmospheric pressure, reducing the risk of leakage.
The primary purpose of PRISM is burning up spent nuclear fuel from other reactors, rather than breeding new fuel. Options include a range of plant ratings, including a "battery" of 50 to MW of electricity that features a very long refueling interval, a modular system rated at to MW, and a large monolithic plant option at 1, MW The term battery refers to the long-life, factory-fabricated core, not to any provision for electrochemical energy conversion.
The fuel is metal or nitride-based containing fertile uranium and transuranics. The higher temperature enables the production of hydrogen by thermochemical processes. A reduced-power model of Myrrha called Guinevere was started up at Mol in March The GEN IV Forum shifts from the paradigm that nuclear accidents can occur and should be "mastered" to the principle of "excluding accidents". They contend that the combination of active and passive nuclear safety systems in Generation IV systems would be at least as effective as those of Generation III systems and render the most severe accident physically impossible because they have inherent safety.
Relative to current nuclear power plant technology, the claimed benefits for 4th generation reactors include:. Nuclear reactors do not emit CO 2 during operation, although like all low carbon power sources, the mining and construction phase can result in CO 2 emissions, if energy sources which are not carbon neutral such as fossil fuels , or CO 2 emitting cements are used during the construction process.
A Yale University review published in the Journal of Industrial Ecology analyzing CO 2 life cycle assessment LCA emissions from nuclear power stated that "the collective LCA literature indicates that life cycle GHG [greenhouse gas] emissions from nuclear power are only a fraction of traditional fossil sources and comparable to renewable technologies.
A specific risk of the sodium-cooled fast reactor is related to using metallic sodium as a coolant. In case of a breach, sodium explosively reacts with water. Fixing breaches may also prove dangerous, as the cheapest noble gas argon is also used to prevent sodium oxidation. Argon, like helium, can displace oxygen in the air and can pose hypoxia concerns, so workers may be exposed to this additional risk. Disadvantages of lead compared to sodium are much higher viscosity, much higher density, lower heat capacity, and more radioactive neutron activation products.
In many cases, there is already a large amount of experience built up with numerous proof of concept Gen IV designs. For example, the reactors at Fort St. Nuclear engineer David Lochbaum cautions that safety risks may be greater initially as reactor operators have little experience with the new design "the problem with new reactors and accidents is twofold: scenarios arise that are impossible to plan for in simulations; and humans make mistakes".
The technology may be proven, but people are not". From Wikipedia, the free encyclopedia. New nuclear reactor technologies under development. This section needs to be updated. Please help update this article to reflect recent events or newly available information. August Main article: Molten salt reactor. See also: Liquid fluoride thorium reactor.
Main article: Supercritical water reactor. Main article: Gas-cooled fast reactor. Main article: Sodium-cooled fast reactor. Main article: Lead-cooled fast reactor.
Energy portal Nuclear technology portal. Energy Policy. Nuclear Technology. S2CID Retrieved March 22, Scientific American. Retrieved
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