Introduction condition of a tokamak fusion power plant as an advanced technology in world energy scenarioR.Hiwatari, K.Tokimatsu, Y.Asaoka, K.Okano, S.Konishi and Y.OgawaUS-Japan Workshop on Fusion Power Plant and Related Advanced Technology with participation of EU Center for Promotion of Computational Science and Engineering, JAERIJan. 11, 2005, Tokyo, JapanCentral Research Institute of Electric Power Industry (CRIEPI), Tokyo, JapanResearch Institute for Innovative Technology for the Earth (RITE), Tokyo, JapanInstitute of Advanced Energy, Kyoto Univ., Kyoto, JapanHigh Temperature Plasma Center, the Univ. of Tokyo, Tokyo, Japan

ContentsUS-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyIntroduction and objectives electric and economic break-even conditions in the fusion energy development World energy scenario and break-even price of fusion energyAnalysis method of electric and economic break-even conditionElectric break-even condition Completion of this condition leads to recognize fusion energy as a suitable candidate of an alternative energy source in world energy scenario.Economic break-even conditionCompletion of this condition leads for fusion energy to be selected as an alternative energy source Summary

IntroductionUS-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyThree Milestone of Fusion Energy DevelopmentDiscussed as an important issueCommercial ReactorCRESTA-SSTR2, ARIES-AT etcIntroduction into marketDemonstration ReactorDevelopment PathBreakeven conditionElectric breakeven conditionGross electric power is larger than circulating powerEconomic breakeven conditionCost Competition with other energy sourcesRecognized as a suitable candidate of an alternative energy in a long term energy scenarioSelected as an alternative energy in a long term energy scenarioDemo. ReactorProto. Reactor

ObjectivesUS-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyThe present study reveals the following two introduction conditions of a tokamak fusion power plant in a long term energy scenario.

(1)Electric breakeven condition, which is required for the fusion energy to be recognized as a suitable candidate of an alternative energy

(2)Economic breakeven condition, which is required to selected as an alternative energy source

World Energy ScenarioUS-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyBreak-even Pricein 2050 is estimated at 65mill/kWh135mill/kWhLong term world energy and model (Linearized DNE21) is applied to the fusion energy. (This model is used for IPCC post SRES activity.) Under the condition of 550 ppm CO2 concentration in atmosphere, breakeven price and introduction year are analyzed.If the COE for the fusion energy can achieve the 65mill/kWh, 20% share of the fusion energy in all produced electricity in 2100 is expected.Economic Breakeven condition in this study.

Analysis Method0D plasma model of ITERPhysics Guidelines simple engineering model based on TRESCODE(JAERI)Generomak Model for economic analysisbN, GW, HH required to achieve electric and economic break-even conditionPlasma size(major radiusaspect ratio)major physical parametersshape and location of reactor component TFCS coilradial buildweight of each component, construction costcost of electricity (COE)FUSAC (FUsion power plant System Analysis Code)Database of 10,000 operation points for a tokamakElectric and economic break-even conditionUS-Japan Workshop on Fusion Power Plant and Related Advanced Technology

Parameter RegionPlasma sizeMaximum is ITER-FDR(8.5m).Max. Magnetic fieldThermal efficiencyNBI system efficiencyThe coolant conditions of ITER test blanket module 30%The outlook of R&D for Ni3Al 16TThe outlook of NBI system in ITER (40%) 50%NBI power for current drive restricted to 200MW.1.4m for blanket and shield region was kept.Current ramp-up is induced by CS coils.Other conditionsUS-Japan Workshop on Fusion Power Plant and Related Advanced Technology

R (m)5.58.5A2.64.01.8, 1.9, 2.00.35, 0.45Te(=Ti) (keV)12203.06.0Btmax (T)13, 1619e (%)3040 (%)30, 5070

Plasma Performance Required to Generate Net Electric Power ---N---US-Japan Workshop on Fusion Power Plant and Related Advanced Technology required for net electric powerEffect of restriction PNBIThe operational region is enlarged with the increasing the restriction PNBI Penet=1000 MW case PNBI100 MW and 3.5N PNBI 300 MW and 2.7 N ITER inductive operation mode(N=1.8) corresponds to Penet=0MW regionPenet=0 MWPenet=1000 MW1.22.73.05.8

US-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyPlasma Performance Required to Generate Net Electric Power ---HH---Effect of restriction PNBIITER inductive operation mode(HH=1.0) is included in Penet=0MW regionPenet=0 MWPenet=1000 MW0.8HH2.20.9HH1.6HH required for net electric powerThe operational region is enlarged with the increasing the restriction PNBI Penet=1000 MW case PNBI100 MW and 1.1HH PNBI 300 MW and 0.8 HH

US-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyPlasma Performance Required to Generate Net Electric Power ---fnGW---Penet=0 MWPenet=1000 MW0.41.10.92.0fnGW required for net electric powerEffect of restriction PNBIITER inductive operation mode(fnGW=0.85) corresponds to Penet=0MW regionThe effect of restriction PNBI is not described in case of the required fnGW

US-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyCorrelation between Plasma Performances and and and Both and have to be increased together so as to increase the net electric powerNo clear relationshipNo clear relationshipThere is no operational point under HH0.8, of course, which is depending on the ristriction PNBIExistence of inevitable HH value

Plasma Performance Diagram for the Net Electric Power Generation ---R=8.5m---US-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyPenet=0 MW and Pf=1000 MWPenet=600 MW and Pf=3000 MWN=1.5, HH=1.0N=3.0, HH=1.15N and fnGW HHRequirement to increase PenetIncrease togetherNot necessary to increaseDepending on the restriction PNBIIn comparison with the present ITER experimental planThe outlook of both Penet =0MW and Penet=600 MW will be obtained.

Plasma Performance Diagram for the Net Electric Power Generation ---R=7.5m--- US-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyPenet=0 MW and Pf=1000 MWPenet=600 MW and Pf=3000 MWN=1.9, HH=1.0N=3.4, HH=1.15In comparison with the present ITER experimental planThe outlook of both Penet =0MW and Penet=600 MW will be obtained.

Plasma Performance Diagram for the Net Electric Power Generation ---R=6.5m--- US-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyPenet=0 MW and Pf=1000 MWPenet=600 MW and Pf=3000 MWN=2.3, HH=1.0N=3.8, HH=1.15In comparison with the present ITER experimental planThe outlook of Penet =0MW will be obtained, but it is difficult to achieve Penet=600MW.

Electric break-even conditionUS-Japan Workshop on Fusion Power Plant and Related Advanced Technology= 1.9 Btmax=16 T e=30% NBI=50%Typical electric breakeven condition How small device is feasible for Demo depends on how high plasma performance is achieved in ITER Typical operation point for each major radius and each net electric power in the previous figures. HH1.0 for Penet=0MW operation points HH1.2 for Penet=600MW operation pointsITER experimental region covers wide range of operation point from bN=1.8 to bN= 3.6.

Advancement of engineering conditionUS-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyEngineering Conditions for economic break-even conditionBtmax=16The=40Penet=1000MWe other condition are the same as the previous electric breakeven analysis.Plant availability 60%, an unexpected outage is consideredIncluding without CS coil case(CS-less case), Note that full non-inductive current ramp-up is required

Economic break-even condition bNUS-Japan Workshop on Fusion Power Plant and Related Advanced TechnologybN required for breakeven priceHigher limit of breakeven price (135mil/kWh)bN2.5 is requiredLower limit of breakeven price (60mil/kWh)bN5.0 and Rp

Economic break-even condition HHUS-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyHH required for breakeven priceThe higher HH is the lower COE is, because of reduction of the cost for the current drive system.In contrast with bN, the required HH region is almost the same through the range of 5.5m

Dependence of COE on BtmaxUS-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyThe increase of Btmax is very effective for the mitigation of the required bN under the condition of including the simplified radial build without a CS coil.The increase of Btmax increases the lowest limit of COE under the condition of the same critical current density of TF coils, because the increase of the coil volume or the device size, and the lower limit of COE range of 19T increases up to 90mill/kWh. CREST (Rp=5.4, he41%, Btmax=13T) is near the breakeven price of 65mill/kWhTo get the merit of high magnetic field, the current density of super conductor also has to be improved. When current density about 20MW/m2 of TF coils is feasible with the same cost as a 10MA/m2 coil, the merit of high field is clearly seen.

SummaryUS-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyElectric Breakeven conditionbN2.0, HH1.0steady state operation techniquemax. magnetic field 16Tthermal efficiency he=30% lead to achieve the electric breakeven condition.The electric breakeven condition requires the simultaneous achievement of 1.2

System Analysis Code (FUSAC)US-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyOutput of ResultCalculation Flowelevation viewradial buildplane view

fnGW and Operation Temperature US-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyThe required fnGW decreased with increasing operation temperature.

N is almost constant.fnGW

Confinement and MHD propertyNBI current drive propertyDivertor operation conditionThe operation temperature will be optimizedconsistency

The effect of thermal efficiencyUS-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyR=7.5 m and e=40% casePenet=0 MW and Pf=1000 MWPenet=900 MW and Pf=3000 MWN=1.5, HH=0.9N=3.4, HH=1.15The e progress will decrease the required plasma performances with the same Penet , or increase the net electric power with the same plasma performanceR=7.5 m and e=40 % caseTo get the economical outlook, the e progress is inevitable.

The effect of NBI system efficiencyUS-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyR=7.5 m and e=40% casePenet=0 MW and Pf=1000 MWPenet=450 MW and Pf=3000 MWN=1.8, HH=1.4N=3.4, HH=1.15The NBI is critical to the required HH, especially, in the low Penet region. R=7.5 m and NBI=30 % caseThe e progress should be almost completed by the demo reactor stage.

The effect of Max. magnetic fieldUS-Japan Workshop on Fusion Power Plant and Related Advanced TechnologyIncrease of Btmax from 13T to 19TThe required N decreaseThe operational region is shrankIn case of Btmax=19T, the current ramp-up is not possible by CS coil, or 1.4m space for blanket and shield can not be accommodated (R