generation iii reactor
generation iii reactor
The initial certification in 1997 was for 15 years and in 2011 the NRC certified for GE Hitachi an evolved version which allows for aircraft impacts. Initial seed (and possibly all) MOX fuel needs to have about 10% Pu. GE Hitachi was also designing a 600-800 MWe version of the ABWR, with five instead of ten internal coolant pumps, aiming at Southeast Asia. 7 These improvements are in the areas of fuel technology, thermal efficiency, modularized construction, safety systems (especially the use of passive rather than active systems), and standardized design. The 280 MWe A related development has been the merging of accelerator and fission reactor technologies to generate electricity and transmute long-lived radioactive wastes.A high-energy proton beam hitting a heavy metal target produces neutrons by spallation.
It is not clear whether Mitsubishi Heavy Industries might be involved, though Areva has said that it wants the design "to have the highest possible technical convergence" with Atmea1. It has been developed by Candu Energy with CNNC’s Third Qinshan Nuclear Power Corp, which plans to convert the two Qinshan CANDU-6 PHWR units to AFCRs. It was the basis of the Korean Next Generation Reactor programme and many of its design features are incorporated into eight South Korean reactors, specifically the APR1400, which is operating in South Korea and being built in South Korea and the UAE and marketed worldwide.Another, more innovative US advanced reactor was smaller – 600 MWe – and had passive safety features (its projected core damage frequency is more than 100 times less than NRC requirements). The nuclear power industry has been developing and improving reactor technology for more than five decades and is starting to build the next generation of nuclear power reactors to fill new orders.Several generations of reactors are commonly distinguished. The NRC confirmed its safety in September 2018 and design certification was approved in May 2019 and formally awarded in August.Based on this, KOPEC has developed an EU version (APR1400-EUR or EU-APR) with double containment and core-catcher which was given EUR approval in October 2017. As well as natural uranium, it can use direct recovered/reprocessed uranium (RU) from used PWR fuel, natural uranium equivalent (NUE – DU + RU), MOX (DU + Pu), fertile fuels such as LEU + thorium and Th with Pu, and closed cycle fuels (Th + U-233 + Pu). It is 1250 MWe gross and 1110-1117 MWe net in the USA, 1157 or 1170 MWe net in China (3415 MWt). The means that many small components are assembled in a factory environment (offsite or onsite) into structural modules weighing up to 1000 tonnes, and these can be hoisted into place. The US-APWR was selected by Luminant for Comanche Peak, Texas, a merchant plant.Fuel in 241 fuel assemblies has burnable poison and will have up to 55 GWd/t burn-up, refuelling cycle around 18 months, outlet temperature 324ºC. The reactor is simpler overall and uses high-burnup fuels (to 65 GWd/t) enriched to 3.54%, giving it refuelling intervals of up to 24 months. Two examples built by Hitachi and two by Toshiba have been in commercial operation in Japan (1315 MWe net), with another two under construction there and two in Taiwan. UK generic design assessment approval for Hitachi's version of the ABWR is expected at the end of 2017. A Generation III reactor is a development o Generation II nuclear reactor designs incorporating evolutionary improvements in design developed during the lifetime o the Generation II reactor designs. Passive safety features do not require external power sources to be effective. Hitachi has also been closely involved, with its RBWR concept which has a major aim of burning actinides.A new reprocessing technology is part of the RMWR concept. In this, 90-92% of the uranium in the used fuel is volatalised as UF6, then purified for enrichment or storage. This is surrounded by layers of carbon and silicon carbide, giving a containment for fission products which is stable to 1600°C or more. Considering the BWR variant (resource-renewable BWR – RBWR), only the fuel assemblies and control rods are different. It is also being built in Pakistan.CNNC and CGN in December 2015 formed a 50-50 joint venture company – Hualong International Nuclear Power Technology Co – to market it. Generation III Gen III nuclear reactors are essentially Gen II reactors with evolutionary, state-of-the-art design improvements. European Utility Requirements (EUR) since 2001 specify that new reactor designs must be capable of load-following between 50 and 100% of capacity. There is much hope for generation IV reactors in terms of sustainability, safety, and price. The residual is put through a Purex circuit which separates fission products and minor actinides as high-level waste, leaving the unseparated U-Pu mix (about 4:1) to be made into MOX fuel.Hitachi conducted joint research on RBWRs with MIT, University of Michigan, and UC Berkeley from 2007 to 2011, on the burning of transuranic elements. All of these operate at higher temperatures than today's reactors. In both, long-term decay heat removal does not rely on electrical power or ultimate heat sink. Planned for Akkuyu in Turkey (V-509).While Gidropress is responsible for the actual 1200 MWe reactor, Moscow AEP and Atomproekt St Petersburg are going different ways on the cooling systems, and the V-392M version is the basis of the VVER-TOI.
It has three coolant loops delivering 3050 MWt, 1170 MWe gross, 1090 MWe net (CNNC version).
OKBM envisages about 11 GWe of such plants by 2030, including South Urals nuclear plant.
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