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Dirty South. Hip Hop. Acoustic House. Drum and Bass. Dub Techno. Bass House. Instrument Models. Big Room. Sound Effects. Jump Style. Tech House. Chicago House. Chill Hop. Festival House. Melbourne Bounce. Future Bass. Trip Hop. Future Bounce. Future House. Tropical House. Circuit Bending. Future Pop. Neo Soul. Vocal Samples. Future Wobble. Nu Disco. Maschine Samples.
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V Station. Valentine’s Day Drums Rack. Dune 2. Logic Pro Templates. Editor’s Pick. Ableton Live Tutorials. Liquid Notes Tutorials. Reaktor Tutorials. Ableton Push. Dune Tutorials. Reason Absynth Tutorials. Logic Pro X Tutorials. Access Virus Tutorials. Maschine Jam. Rounds Tutorials. Fab Filter Pro R. Maschine Tutorials. First Look. Massive Tutorials. There are a ton of extras, and it all feels, for lack of a better word, totally Reaktor-ish.
Why yes, thank you, I would like to make IDM for the rest of the night. Glad you asked. In a dark and complex world, what better than to disappear into headphones and listen to the sound of gently morphing oscillators, I ask you…. The block is a real Swiss Army knife: it can be used to draw or record modulation, used as a drawable audio-rate oscillator, used as part of a generative music patch, used for recording and storing notes of a sequence, generating clocks and much more.
Similar to the above — give them your email address, get a download. Modular-Analog Software Stories Tech. Peter Kirn – August 24, Add comment.
Completely free, no Reaktor needed The situation for modules has changed in Reaktor-land recently. Reaktor 6. Tags: modular , Reaktor , software modular. Previous post Remembering house and techno legend Aaron Carl, in an intimate portrait. Next post Reason Friktion review: an exquisitely playable physical modeling string instrument.
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With thorium, it is possible to breed using a thermal reactor. This was proven to work in the Shippingport Atomic Power Station , whose final fuel load bred slightly more fissile from thorium than it consumed, despite being a fairly standard light water reactor.
Thermal reactors require less of the expensive fissile fuel to start, but are more sensitive to fission products left in the core. There are two ways to configure a breeder reactor to do the required breeding. One can place the fertile and fissile fuel together, so breeding and splitting occurs in the same place.
Alternatively, fissile and fertile can be separated. The latter is known as core-and-blanket, because a fissile core produces the heat and neutrons while a separate blanket does all the breeding. Oak Ridge investigated both ways to make a breeder for their molten salt breeder reactor. Because the fuel is liquid, they are called the “single fluid” and “two fluid” thorium thermal breeder molten salt reactors. The one-fluid design includes a large reactor vessel filled with fluoride salt containing thorium and uranium.
Graphite rods immersed in the salt function as a moderator and to guide the flow of salt. In the ORNL MSBR molten salt breeder reactor design [18] a reduced amount of graphite near the edge of the reactor core would make the outer region under-moderated, and increased the capture of neutrons there by the thorium. With this arrangement, most of the neutrons were generated at some distance from the reactor boundary, and reduced the neutron leakage to an acceptable level.
In a breeder configuration, extensive fuel processing was specified to remove fission products from the fuel salt. The MSRE was a core region only prototype reactor.
According to estimates of Japanese scientists, a single fluid LFTR program could be achieved through a relatively modest investment of roughly — million dollars over 5—10 years to fund research to fill minor technical gaps and build a small reactor prototype comparable to the MSRE.
The two-fluid design is mechanically more complicated than the “single fluid” reactor design. The “two fluid” reactor has a high-neutron-density core that burns uranium from the thorium fuel cycle.
A separate blanket of thorium salt absorbs neutrons and slowly converts its thorium to protactinium Protactinium can be left in the blanket region where neutron flux is lower, so that it slowly decays to U fissile fuel, [23] rather than capture neutrons.
This bred fissile U can be recovered by injecting additional fluorine to create uranium hexafluoride, a gas which can be captured as it comes out of solution. Once reduced again to uranium tetrafluoride, a solid, it can be mixed into the core salt medium to fission.
The core’s salt is also purified, first by fluorination to remove uranium, then vacuum distillation to remove and reuse the carrier salts. The still bottoms left after the distillation are the fission products waste of a LFTR. One weakness of the two-fluid design is the necessity of periodically replacing the core-blanket barrier due to fast neutron damage. The effect of neutron radiation on graphite is to slowly shrink and then swell it, causing an increase in porosity and a deterioration in physical properties.
Another weakness of the two-fluid design is its complex plumbing. ORNL thought a complex interleaving of core and blanket tubes was necessary to achieve a high power level with acceptably low power density. However, more recent research has questioned the need for ORNL’s complex interleaving graphite tubing, suggesting a simple elongated tube-in-shell reactor that would allow high power output without complex tubing, accommodate thermal expansion, and permit tube replacement.
A two fluid reactor that has thorium in the fuel salt is sometimes called a “one and a half fluid” reactor, or 1. Like the 1 fluid reactor, it has thorium in the fuel salt, which complicates the fuel processing. And yet, like the 2 fluid reactor, it can use a highly effective separate blanket to absorb neutrons that leak from the core. The added disadvantage of keeping the fluids separate using a barrier remains, but with thorium present in the fuel salt there are fewer neutrons that must pass through this barrier into the blanket fluid.
This results in less damage to the barrier. Any leak in the barrier would also be of lower consequence, as the processing system must already deal with thorium in the core. The main design question when deciding between a one and a half or two fluid LFTR is whether a more complicated reprocessing or a more demanding structural barrier will be easier to solve.
In addition to electricity generation , concentrated thermal energy from the high-temperature LFTR can be used as high-grade industrial process heat for many uses, such as ammonia production with the Haber process or thermal Hydrogen production by water splitting, eliminating the efficiency loss of first converting to electricity.
The Rankine cycle is the most basic thermodynamic power cycle. The simplest cycle consists of a steam generator , a turbine, a condenser, and a pump. The working fluid is usually water. A Rankine power conversion system coupled to a LFTR could take advantage of increased steam temperature to improve its thermal efficiency. The Brayton cycle generator has a much smaller footprint than the Rankine cycle, lower cost and higher thermal efficiency, but requires higher operating temperatures.
It is therefore particularly suitable for use with a LFTR. The working gas can be helium, nitrogen, or carbon dioxide.
The low-pressure warm gas is cooled in an ambient cooler. The low-pressure cold gas is compressed to the high-pressure of the system. The high-pressure working gas is expanded in a turbine to produce power. Often the turbine and the compressor are mechanically connected through a single shaft. A Brayton cycle heat engine can operate at lower pressure with wider diameter piping. The LFTR needs a mechanism to remove the fission products from the fuel.
Fission products left in the reactor absorb neutrons and thus reduce neutron economy. This is especially important in the thorium fuel cycle with few spare neutrons and a thermal neutron spectrum, where absorption is strong. The minimum requirement is to recover the valuable fissile material from used fuel. Removal of fission products is similar to reprocessing of solid fuel elements; by chemical or physical means, the valuable fissile fuel is separated from the waste fission products.
Ideally the fertile fuel thorium or U and other fuel components e. However, for economic reasons they may also end up in the waste. On site processing is planned to work continuously, cleaning a small fraction of the salt every day and sending it back to the reactor.
There is no need to make the fuel salt very clean; the purpose is to keep the concentration of fission products and other impurities e.
The concentrations of some of the rare earth elements must be especially kept low, as they have a large absorption cross section. Some other elements with a small cross section like Cs or Zr may accumulate over years of operation before they are removed. As the fuel of a LFTR is a molten salt mixture, it is attractive to use pyroprocessing , high temperature methods working directly with the hot molten salt.
Pyroprocessing does not use radiation sensitive solvents and is not easily disturbed by decay heat. It can be used on highly radioactive fuel directly from the reactor. Ideally everything except new fuel thorium and waste fission products stays inside the plant. One potential advantage of a liquid fuel is that it not only facilitates separating fission-products from the fuel, but also isolating individual fission products from one another, which is lucrative for isotopes that are scarce and in high-demand for various industrial radiation sources for testing welds via radiography , agricultural sterilizing produce via irradiation , and medical uses Molybdenum which decays into Technetiumm , a valuable radiolabel dye for marking cancerous cells in medical scans.
The more noble metals Pd , Ru , Ag , Mo , Nb , Sb , Tc do not form fluorides in the normal salt, but instead fine colloidal metallic particles. They can plate out on metal surfaces like the heat exchanger, or preferably on high surface area filters which are easier to replace.
Still, there is some uncertainty where they end up, as the MSRE only provided a relatively short operating experience and independent laboratory experiments are difficult. Gases like Xe and Kr come out easily with a sparge of helium. In addition, some of the “noble” metals are removed as an aerosol. The quick removal of Xe is particularly important, as it is a very strong neutron poison and makes reactor control more difficult if unremoved; this also improves neutron economy.
The gas mainly He, Xe and Kr is held for about 2 days until almost all Xe and other short lived isotopes have decayed. Most of the gas can then be recycled. After an additional hold up of several months, radioactivity is low enough to separate the gas at low temperatures into helium for reuse , xenon for sale and krypton, which needs storage e. For cleaning the salt mixture several methods of chemical separation were proposed. The pyroprocesses of the LFTR salt already starts with a suitable liquid form, so it may be less expensive than using solid oxide fuels.
However, because no complete molten salt reprocessing plant has been built, all testing has been limited to the laboratory, and with only a few elements. There is still more research and development needed to improve separation and make reprocessing more economically viable. Uranium and some other elements can be removed from the salt by a process called fluorine volatility: A sparge of fluorine removes volatile high- valence fluorides as a gas.
This is mainly uranium hexafluoride , containing the uranium fuel, but also neptunium hexafluoride , technetium hexafluoride and selenium hexafluoride , as well as fluorides of some other fission products e.
The volatile fluorides can be further separated by adsorption and distillation. Handling uranium hexafluoride is well established in enrichment. The higher valence fluorides are quite corrosive at high temperatures and require more resistant materials than Hastelloy. At the MSRE reactor fluorine volatility was used to remove uranium from the fuel salt. Also for use with solid fuel elements fluorine volatility is quite well developed and tested.
Another simple method, tested during the MSRE program, is high temperature vacuum distillation. The lower boiling point fluorides like uranium tetrafluoride and the LiF and BeF carrier salt can be removed by distillation. Under vacuum the temperature can be lower than the ambient pressure boiling point. The chemical separation for the 2-fluid designs, using uranium as a fissile fuel can work with these two relatively simple processes: [35] Uranium from the blanket salt can be removed by fluorine volatility, and transferred to the core salt.
To remove the fissile products from the core salt, first the uranium is removed via fluorine volatility. Then the carrier salt can be recovered by high temperature distillation. The fluorides with a high boiling point, including the lanthanides stay behind as waste.
The early Oak Ridge’s chemistry designs were not concerned with proliferation and aimed for fast breeding. They planned to separate and store protactinium , so it could decay to uranium without being destroyed by neutron capture in the reactor.
The protactinium removal step is not required per se for a LFTR. Alternate solutions are operating at a lower power density and thus a larger fissile inventory for 1 or 1. 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.
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