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Development of...Continued from page 39minimizing the scope of possible loss ofcoolant accidents (LOCA) and reactivityinitiated accidents (RIA). The ArgentinianCAREM (from Spanish: CentralARgentina de Elementos Modulares)reactor is cooled by natural circulation,and has passive safety systems. Argentinaplans to construct and operate a smallprototype of 27 MW(e) by about 2011,followed by larger projects with higherpower ratings of up to ~300 MWe. TheSMART (System Integrated ModularAdvanced Reactor) 330 MWt designdeveloped in the Republic of Korea is anintegral PWR for electricity productionand seawater desalination. Constructionof a pilot or demonstration plant isplanned. The IRIS design of integraltype pressurized water reactor developedby an International consortium led byWestinghouse Electric Company (USA)has unit power of 335 MW(e) but allowsfor twin unit NPPs. It is entering thedetailed design stage and its designcertification by the US NRC is scheduledto start in 2012. As another example, theNuScale company in the USA is designinga 45 MWe small integral PWR for amulti-modular NPP of 540 MWe. Morerecently, B&W announced their plansto deploy by 2018 their new 125 MWeintegral reactor design, the mPower, witha refueling cycle of 5 years.In Russia, the Experimental DesignBureau of Machine Building (OKBM) hasdeveloped the KLT-40S, a small bargemountedNPP design for electricity andheat, for which construction was startedin June 2006. Assembly of the first reactorfor the floating plant was completed inearly 2009 and the assembly of the secondone is well underway. The floating plantwill deliver 300 MWt/70 MWe with twowater cooled KLT-40S reactors on board.Activities are in full swing by theKazakhstan Russian joint venture tofinalize detailed design of the VBER-300 reactor of 295 MW(e) for a landbased cogeneration plant, also allowingfor twin units. VBER-300 is essentially alarger version of the KLT-40S, and couldalso be located on a barge. There areplans to build the first VBER-300 units inKazakhstan before 2015, and sites for thelocation of these plants have already beenselected.In Japan, the Toshiba Corporation,in cooperation with the Central ResearchInstitute of Electric Power Industry(CRIEPI) and Westinghouse ElectricCompany, is developing the 4S sodiumcooled reactor. It has a design power of10 MW(e) and a refueling interval of30 years. The US Nuclear RegulatoryCommission began a pre-applicationreview in 2007, and the formal licensingprocess is scheduled to start in October2010. Construction of a demonstrationreactor and safety tests are planned forthe first half of the next decade.Innovative SMRs are underdevelopment for all principal reactorlines and some non-conventionalcombinations. More than 45 innovativeSMR concepts and designs are at differentstages of development within nationalor international R&D programmes,involving both developed and developingNPJ Advertiser Web DirectoryAREVA NP, Inc.www.us.areva.comBechtel Powerwww.bechtel.comBlack & Veatchwww.bv.comCeradynewww.ceradyneboron.comEnertech,a business unit of Curtiss-WrightFlow Control Companyenertech.cwfc.comHSB Global Standardswww.hsbgsnuclear.comKinectrics Inc.www.kinectrics.comNACE Internationalwww.nace.org/nuclearNuclear Logistics Inc.www.nuclearlogistics.comPower House Tool, Inc.www.powerhousetool.comRadiation Protection Systems,Inc. (RPS)www.rpsct.comRolls-Roycewww.rolls-royce.comSeal Masterwww.sealmaster.comThe Babcock & WilcoxCompanywww.babcock.comThermo Fisher Scientific,Scientific Instruments DivisionCIDTEC Cameras & Imagerswww.thermo.com/cidtecTrentec,a business unit of Curtiss-WrightFlow Control Companywww.trentec.comUniStar Nuclear Energywww.unistarnuclear.comUrenco Enrichment CompanyLtd.www.urenco.comWesterman Nuclearwww.westermancompanies.comWestern Space and Marine, Inc.www.wsminc.comWestinghouse ElectricCompany LLCwww.westinghousenuclear.comWM Symposia, Inc.www.wmsym.orgZachry Nuclear Engineering,Incwww.zhi.comZetec, Inc.www.zetec.com40 www.NuclearPlantJournal.com Nuclear Plant Journal, September-October 2009
countries. Most allow for, or explicitlyfacilitate, non-electrical applications suchas potable water or hydrogen production.Fast reactorsFast reactors have been underdevelopment for many years in severalcountries, primarily as breeders.Plutonium breeding allows fast reactors toextract sixty-to-seventy times more energyfrom uranium than thermal reactors do - acapability that will allow very substantialincreases in nuclear power in the longerterm. Fast reactors can also contributeto reducing plutonium stockpiles, and toreducing the required isolation time forhigh-level radioactive waste by utilizingtransuranic radioisotopes and transmutingsome long-lived fission products.The design and operation of sodiumcooledfast reactors, such as the smallsize Prototype Fast Reactor in the UnitedKingdom, the prototype Phénix inFrance, the BN-350 in Kazakstan (part ofits thermal energy was used for sea-waterdesalination), the demonstration BN-600 in Russia, Monju in Japan, and thecommercial size Superphénix in France,have provided an experience base of morethan 400 reactor-years. In addition, thereis a considerable base of experience withlead-bismuth (eutectic) cooled propulsion(submarine) reactors operated in Russia.Currently there are two experimentalfast reactors in operation (BOR-60 andFBTR) and one under commissioning(CEFR); one power fast reactor inoperation (BN-600), one under re-startpreparation (Monju), one in the stage ofend-of-life tests (Phénix), and two underconstruction (PFBR and BN-800).Examples of current activities include:completion of the construction in China ofthe small size Chinese Experimental FastReactor with criticality scheduled for fall2009; the development of the medium sizeKALIMER 600 design in the Republicof Korea; the successful operation ofthe Indian Fast Breeder Test Reactorand its utilization for fast reactor R&D,especially fuel irradiation and materialsresearch; the medium size PrototypeFBR in India for which constructionstarted in 2004 and commissioning isplanned for 2010- 2011; and, in France,the end-of-life experimental programmeat Phénix that will be shut down in fallof 2009, as well as design work for amedium size new generation fast reactor(ASTRID), as a test-bed for system andtechnological innovation, having thecapability for materials and fuel testing,and demonstration of advanced recyclestrategies.In China, component installationwork for the pool-type China ExperimentalFast Reactor (CEFR, 65MWth/20MWe)was completed. Two hundred-fifty tonsof nuclear grade high purity sodium wasshipped to the plant. Filling of the primaryand secondary loops was completed inApril 2009. Fuel loading was planned tostart by August 2009, with first criticalitybefore the end of the year. Grid connectionat 30% power is planned for mid-2010.France just completed the definitionof the test program in view of the final shutdownof the 280 MWe fast reactor Phénix.Research and technology developmentactivities are ongoing in two areas: thegas-cooled and the sodium-cooled fastreactor concepts. France is planning anexperimental reactor (ETDR, possiblyas an European project) in the range of50 MWth to demonstrate the viability ofkey gas-cooled fast reactor technologies.Patented mobile shield panelssave hundreds of man-hours overtraditional concrete block orbuilt up shield walls. Roll in place positioning. Lockable security barrier. Gamma/Neutron attenuation Immediate exposure andcost savings!For the sodium-cooled concept, designwork is ongoing for the 250 – 600 MWeGEN IV prototype sodium-cooled fastreactor ASTRID (to be commissionedin 2020), as a test-bed for system andtechnological innovation, having thecapability for materials and fuel testing,and demonstration of advanced recyclestrategies.In India, the design and analysis ofall major systems and components ofthe 500 MWe Prototype Fast BreederReactor (PFBR, under construction atKalpakkam) have been completed. At thesame time, R&D activities in the fields ofreactor physics, component development,thermal hydraulics, structural mechanics,materials and metallurgy, safety, fuelchemistry and reprocessing are focusedtowards future fast breeder reactors. Forclosing the fuel cycle, a Fast ReactorFuel Cycle Facility (FRFCF) is underconstruction at Kalpakkam. The layoutof the FRFCF has been planned in sucha way that expansion is possible to meetthe requirements of two more 500 MWe(Continued on page 42)Install and remove 35,000 lbs.of shielding in 5 minutes! Significant exposure reductionin outages or in service. Rapid containment access andclosure. Custom designs for anyapplication where repeatablefast access & closure is required.Modular Shield Wall SystemRadiation Protection Systems, Inc. P.O. Box 890, Groton, CT 06340T 888.637.7779 · Email: support@rpsct.com · Web: www.rpsct.comNuclear Plant Journal, September-October 2009 www.NuclearPlantJournal.com 41
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