Search results for "TOKAMAK"

showing 4 items of 54 documents

Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems

2020

Abstract In the frame of the EUROfusion consortium activities the Helium Cooled Pebble Bed (HCPB) and the Water Cooled Lithium Lead (WCLL) concepts are being developed as possible candidates to become driver Breeding Blanket (BB) for the EU DEMO, which aims at the tritium self-sufficiency and net electricity production. The two BB design options encompass water or helium as coolants and solid ceramic with beryllium/beryllides or PbLi as tritium breeder and neutron multipliers. The BB segments have evolved towards a more stable conceptual design taking into account multiple feasibility aspects and requirements imposed by interfacing systems. Possible solutions to improve shielding capabiliti…

TokamakTritium extraction and removalNuclear engineeringchemistry.chemical_elementIsolation valveBlanket7. Clean energy01 natural sciences010305 fluids & plasmaslaw.inventionBreeder (animal)Conceptual designlaw0103 physical sciencesGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringMechanical EngineeringCoolant purificationCoolantElectricity generationNuclear Energy and EngineeringchemistryEnvironmental scienceBreeding blanketBeryllium
researchProduct

Status of EU DEMO heat transport and power conversion systems

2018

Abstract DEMO in Europe is considered to be the nearest-term reactor design to follow ITER and capable of demonstrating production of electricity, operating with a closed fuel-cycle and to be a facilitating machine between ITER and a commercial reactor. The aim of this paper is to show the design progress of the complex system’s “chain” devoted to the extraction of the plasma generated pulsed thermal power and its conversion into electricity delivered to the grid, including the Primary Heat Transport System (PHTS), the Power Conversion System (PCS) and the Intermediate Heat Transport System (IHTS) – provided by an Energy Storage System (ESS) – in between PHTS and PCS, which is introduced fo…

Tokamakbusiness.industryMechanical EngineeringNuclear engineeringThermal power stationBlanketGrid01 natural sciences7. Clean energyEnergy storage010305 fluids & plasmaslaw.inventionNuclear Energy and Engineeringlaw0103 physical sciencesEnvironmental scienceSystems designGeneral Materials ScienceDirect couplingElectricity010306 general physicsbusinessCivil and Structural EngineeringFusion Engineering and Design
researchProduct

Draining and drying process development of the Tokamak Cooling Water System of ITER

2016

Abstract The ITER Organization (IO) developed a thermal-hydraulic (TH) model of the complex first wall and blanket (FW/BLK) cooling channels to determine gas flow rate and pressure required to effectively blow out the water in the FW/BLK. In addition, US ITER conducted experiments for selected geometries of FW/BLK flow channels to predict the blowout parameters. The analysis indicates that as low as 2 MPa of pressure difference over the blanket modules will ensure substantial evacuation of the water in blankets with just a few percent remaining in the blanket flow channels. A limited validation study indicates that the analysis yields less conservative results to compare against data collec…

Validation studyTokamakProcess developmentMechanical EngineeringNuclear engineeringFlow (psychology)First Wall Blanket Draining Process Drying ProcessBlanketBlow out01 natural sciences010305 fluids & plasmasVolumetric flow ratelaw.inventionNuclear Energy and Engineeringlaw0103 physical sciencesWater coolingEnvironmental scienceGeneral Materials Science010306 general physicsSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
researchProduct

Ydinfuusion fysikaaliset perusteet energiantuotannossa ja fuusiolaitteiden kehitys

2016

Kahden atomin, joiden massaluku on alle 60, yhdistymistä yhdeksi atomiksi kutsutaan fuusioksi. Tämän ydinreaktion seurauksena vapautuu valtavasti energiaa ja sen valjastamista ihmiselle hyödyllisen muotoon on tutkittu yli 50 vuoden ajan. Keskeisin tavoite tälle pro gradu -tutkielmalle oli selvittää lämpöydinfuusion fysikaaliset perusteet, minkälaisia merkittäviä läpimurtoja fuusiotutkimuksessa on saavutettu ja toisaalta minkälaisia ratkaisemattomia ongelmia energiantuottoon kykenevän fuusiovoimalan edessä on. Edistysaskelien ja ratkaisemattomien ongelmien osalta keskitytään menestyksekkäimpään koelaitteeseen, tokamakiin. Tähän mennessä erilaisia koejärjestelmiä on ehdotettu useita, mutta to…

fuusiofuusio (ydinreaktiot)tokamakenergiantuotanto
researchProduct