Development Scenario of Tokamak Reactor as long as Early Demonstration of Electric Powe

Development Scenario of Tokamak Reactor as long as Early Demonstration of Electric Powe www.phwiki.com

Development Scenario of Tokamak Reactor as long as Early Demonstration of Electric Powe

Brillhart, Aaron, Host; Meteorologist has reference to this Academic Journal, PHwiki organized this Journal Development Scenario of Tokamak Reactor as long as Early Demonstration of Electric Power Generation US/Japan Workshop on Power Plant Studies in addition to Related Advanced Technologies With EU Participation 24-25 January 200, 584 EBUII (Engineering Building Unit II), UC San Diego, La Jolla, CA R.Hiwatari, Y.Asaoka, K.Okano, T.Kurodaa), S.Moria), K.Shinyab) in addition to Y.Ogawac) Nuclear Technology Research Laboratory, Central Research Institute of Electric Power Industry (CRIEPI), Komae Japan a) Kawasaki Heavy Industries, Ltd., Tokyo, Japan b) AITEL Corporation, Yokohama, Japan c) The University of Tokyo, Kashiwa, Japan 1 Outline Background in addition to Objectives Why is a development scenario required in addition to What is its objectives A development scenario of ITER, Demo-CREST in addition to CREST Characteristics of this development scenario, ITER, Demo-CREST, in addition to CREST Development issues on plasma per as long as mance What is the critical issue on the core plasma per as long as mance in addition to to what extent it has to be developed in each step Development issues on reactor technology What is the critical issue on the reactor technology in addition to to what extent it has to be developed in each step Role of each development program Specification of the role of each development program (ITER, IFMIF, DEMO, inevitable support program) in this development scenario Summary 2 Background Consistent Development Priority Development Time Schedule Development Goal Technological in addition to physical Issue to be completed Development Scenario Specification of the role of each development program Effective Development Road Map to Realize the Fusion Energy Development scenario of tokamk fusion power plant Experimental Reactor ITER Feasibility of net electric power generation From 2015 to 2035 Demonstration Reactor Demonstration of net electric power generation In 2030~2040 Commercial Plant Introduction into market In 2050~ Tokamak devices JT-60U, JET etc Feasibility of burning plasma From 1980’s to present How about the development scenario after the ITER 3

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Objectives Key issues of development scenario Now, the role of development scenario is to show several development path to fusion energy in addition to its critical issues. (If possible, select the master plan in addition to feed back to ITER in addition to other R&D project). 4 Overall Feature of Development Scenario Development scenario of tokamk fusion power plant Experimental Reactor ITER Feasibility of net electric power generation From 2015 to 2035 Tokamak devices JT-60U, JET etc Feasibility of burning plasma From 1980’s to present The demonstration of electric power generation in the 2030’s is focused on. That means Demo-CREST has to be constructed just after or during the ITER project Testing by ITER is an important policy in this development scenario of Demo-CREST in addition to CREST. This leads to the selection of A=3.4. This development scenario is characterized by a advanced tokamak plasma reactor with a water cooled RAF (Reduced Activated Ferritic Steel) blanket system. Commercial Plant CREST Introduction into market In 2050’s Demonstration Reactor Demo-CREST Demonstration of net electric power generation In 2030’s 5 Demonstration Plant : Demo-CREST Principles as long as the Demo-CREST Design to demonstrate electric power generation as soon as possible in a plant scale, with moderate plasma per as long as mance which will be achieved in the early stage of the ITER operation, in addition to with as long as eseeable technologies in addition to materials (Demonstration Phase OP1~OP4) to show a possibility of an economical competitiveness with advanced plasma per as long as mance in addition to high per as long as mance blanket systems, by means of replacing breeding blanket from the basic one to the advanced one (Development Phase OP4, OPRS) 6

Commercial Plant : CREST The aim of CREST design is to show the typical development goal to get the economic competitiveness. 7 Development Scenario of ITER, Demo-CREST, CREST In the demonstration phase of Demo-CREST, the plasma per as long as mance parameters (N, HH, fnGW) completed in ITER are applied to the Demo-CREST operation, step by step In the development phase, the advanced blanket system as long as higher thermal efficiency enable to increase the net electric power, in addition to conducting walls installed in this blanket system break the road to the more advanced plasma per as long as mance such as N>4.0. Table:Electric power in addition to technology advancement in Development scenario by CRIEPI Reactor technology advancement Plasma advancement 8 Development Issue on Plasma Per as long as mance As as long as N in addition to HH, the Demo-CREST parameters are possibe in this HPSS ITER scenario, but fnGW of OP4 as long as Demo-CREST is a little larger than that of ITER. Hence, the physics of density limit in addition to its attainable region should be examined in the ITER program In the development phase of Demo-CREST, the N value is larger than the ideal wall limit of the present ITER design (N~3.8). Hence, this advanced plasma region should be explored, by other support devices in addition to by itself, in addition to this is why we think Support device is required. In case that ITER would be improved to achieve N>4.0, of course, such high per as long as mance plasma should be demonstrated in the ITER burning plasma. Finally, the increase of plasma shape parameters from (k~1.85, d~0.35) to (k~2.0, d~0.5) is required to achieve bN~5.0, however, several improvement as long as positional instability is supposed to be required in the present design of Demo-CREST 9

Development Issue on Plasma MHD Control 10 Development Issue on Heat in addition to Particle Control Peak power load on the targets is limited to qdiv<10MW/m2 One of the key parameters is the upstream SOL density ns One of the control issues is increase of ns without the degradation of core plasma per as long as mance. The radiation power required as long as qdiv<10MW/m2 in addition to its fraction to total heating power gradually increase from ITER, Demo-CREST (from OP1 to OP4), to CREST. Controllability of ns in addition to impurity seeding level consistent with core plasma per as long as mance has to be precisely examined in ITER, in addition to its operational window should be mapped out as long as the next step devises. : radiation fraction : radiation power 11 Development Issue on Superconducting Coil Figure Operating points of superconducting coils constructed so far in addition to the target as long as fusion demo plant[N.Koizumi, et al., 20th IAEA Fusion Energy Conf. IAEA-CN116-FT/P1-7] 12 Development Issue on Blanket Concept Basic blanket Advanced blanket The same outlet coolant condition (15MPa, 603K) as proposed in ITER TBM is applied, in addition to this condition accepts the large breeding zone in addition to the small cooling channel one in the blanket, because of relatively low temperature. In this blanket concept, the local TBR is estimated at 1.48, which allows the net TBR larger than 1.1. In the development phase of Demo-CREST, an advanced coolant condition (25MPa, 773K) with supercritical water, which is also proposed in ITER TBM, is applied. The local TBR of this advanced blanket system is TBR~1.34. Whether this local TBR is enough or not should be con as long as med in the previous demonstration phase. 13 Development Issue on Plasma Control Device ITER Demo-CREST CREST Beam energy Eb~1.0 MeV System efficiency hNBI=30~40% Gyrotron frequency f~170Mz as long as ECCD Steady state operation of the NBI system in addition to the EC one Beam energy Eb~1.5 MeV as long as feasible current control. System efficiency hNBI>50% by developing a plasma neutralizer Gyrotron frequency f~300Mz as long as ECCD Beam energy Eb~2.5 MeV 14 Development Issue on Maintenance Method The h in addition to ling device as long as shielding plugs in ITER can h in addition to le the weight of 40 tons. The full sector removal scheme as long as blanket in addition to divertor systems is applied to the CREST design. The weight of the one sector (1/14 of the torus) is estimated at about 250 tons. The h in addition to ling device is considered as a device scaled up as long as m the one as long as the ITER shielding plug. The maximum weight to be h in addition to led in Demo-CREST is 130 tons of the outer shield The full sector removal scheme is very effective to the plant availability. In the CREST design, the plant availability achievable to more than 80% including an unexpected outage period. However, a system as long as extraction in addition to attachment of the full sector with precise alignment has to be developed in addition to demonstrated like the ITER maintenance system. A larger TF coil A heavier full sector 15

Development Issue on Structure Material Figure Design windows fo the structural materials as long as the DEMO reactor blanket. [M.Seki, et al., Fusion Science in addition to Technology 42(2002)50] 16 Role of Each Development Program as long as Demo-CREST Demonstration Phase (1) Plasma Physics Issues 17 Role of Each Development Program as long as Demo-CREST Demonstration Phase (2) Engineering Issues 18

Role of Each Development Program as long as Demo-CREST Development Phase (1) Plasma Physics Issues 19 Role of Each Development Program as long as Demo-CREST Development Phase (2) Engineering Issues 20 Role of Each Development Program as long as CREST (1) Plasma Physics Issues 21

Role of Each Development Program as long as CREST (2) Engineering Issues 22 Summary We proposed the development scenario of ITER, Demo-CREST, in addition to CREST aiming at the early realization of net electric power generation. This development scenario is characterized by a highly advanced tokamak plasma reactor with a water cooled RAF blanket system. As as long as plasma per as long as mance, MHD control as long as high plasma per as long as mance in addition to heat in addition to particle control are mainly discussed, in addition to the role of each device (ITER, Demo-CREST, Support device) is specified, respectively. The typical development issue on the reactor technology (SC coils, blanket systems, plasma control devices, maintenance systems, structure materials) as long as Demo-CREST in addition to CREST is also picked up, respectively. Such specification of each development role in the development scenario is the starting point to structure the effective development strategy of fusion energy, in addition to this is very helpful to underst in addition to the development priority. 23

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Brillhart, Aaron Host; Meteorologist

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