The Integrated-Blanket-Coil Concept Applied to the Poloidal Field and Blanket Systems of a Tokamak Reactor

Steiner, D.; Block, Robert C.; Malaviya, B.K.

doi:10.13182/fst85-a24519

Cited by 16 publications

(4 citation statements)

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“…at a profile-corrected Lawson parameter, 70 ntg, value consistent with the stipulated average plasma operating temperature, T, typical values being summarized on 1.0(10) 22 2.15(10) 22 3.64(10) 22 5.98(10) 22 9.00 (10) The systems code uses temperature-dependent coil resistivities, p, for four materials of interest: copper, AMAX-copper, aluminum, and lithium, the latter being applicable to the integrated blanket/coil (IBC) concept. 71 The empirical representation of resistivity as a function of conductor temperature T(K) are given by 72 Parameters of this design are summarized in Table 3 design, comparable to HINIMARS, 21 yields MPD a 100 kWe/tonne at I y « 5 MW/ra 2 .…”

mentioning

confidence: 99%

Advanced tokamak reactors based on the spherical torus (ATR/ST). Preliminary design considerations

Miller¹,

Krakowski²,

Bathke³

et al. 1986

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mentioning

confidence: 99%

Advanced tokamak reactors based on the spherical torus (ATR/ST). Preliminary design considerations

Miller¹,

Krakowski²,

Bathke³

et al. 1986

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“…The blanket-and shield-coolant channels are designed with the consideration of heat transfer, blanket energy multiplication, tritium breeding, and shielding requirements. The TITAN-I blanket is configured as an integrated blanket coil (IBC) [104] and serves as the toroidal-field coil and part of the oscillating-field current-drive coils. The heattransfer requirements of the blauket and shield are not as stringent as for the first-wall-…”

Section: Coolant-channel Configurationmentioning

confidence: 99%

“…The divertor and the TF coils of the TITAN-I design are based on the iptegratedblanket-coil (IBO) concept [104]. The TBC concept utilizes the lithium coolant of the primary circuit, flowing in the poloidal direction within the blanket, as the electrical conductor for the divertor and TF coils.…”

Section: Integrated Blanket Coils (Ibcs)mentioning

confidence: 99%

The TITAN reversed-field-pinch fusion reactor study

1990

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The TITAN Reversed-Field-Pinck (RFP) fusion-reactor study is a multi-institutional research effort to determine the technical feasibility and key developmental issues for an RFP fusion reactor operating at high power density, and to determine the poten tial economic (cost of electricity), operational (maintenance and availability), safety and environmental features of high mass-pov IT-density fusion systems. Mass power density (MPD) is defined as the ratio of net electric output to the mass of the fusion power core (FPC). The fusion power core includes the plasma chamber, first wall, blanket, shield, magnets, and related structure. Two different detailed designs, TITAN-I and TITAN-II, have been produced to demon strate the possibility of multiple engineering-design approaches to high-MPD reactors. TITAN-I is a self-cooled lithium design with a vanadium-alloy structure^ TITAN-II is a self-cooled aqueous loop-in-pool design with 9C ferritic steel as the structural material. Both designs would use RFP plasmas operating with essentially the same parameters. Both conceptual reactors are based on the DT fuel cycle, have a net electric output of about 1000MWe, are compact, and have a high MPD of 800 kWe per tonne of FPC. The inherent physical characteristics of the RFP confinement concept make possible compact fusion reactors with such a high mass power density. The TITAN designs would meet the U. S. criteria for the near-surface disposal of radioactive waste (Class C, 1QCFR61) and would achieve a high Level of Safety Assurance with respect to FPC damage by decay afterheat and radioactivity release caused by accidents. Very importantly, a "single-piece" FPC maintenance procedure has been worked out and appears feasible for both designs. Parametric system studies have been used to find cost-optimized designs, to determine the parametric design window associated with each approach, and to assess the sensitivity of the designs to a wide range of physics and engineering requirements and assumptions. The design window for such compact RFP reactors would include machines with neutron wall loadings in the range of 10-20 MW/m 2 with a shallow minimum-COE at about ISMW/m*. Even though operation at the lower end of the this range of wall loading (10-12 MW/n?) is possible, and may be preferable, the TITAN study adopted the design point at the upper end (18MW/rr&) in order to quantify and assess the technical feasibility and physics limits for such high-MPD reactors. From this work, key physics and engineering issues central to achieving reactors with the features of TITAN-I and TITAN-H have emerged.

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“…Previous work [1] has suggested the use of integrated blanket toroidal field coils (IBC) with stagnant liquid lithium. Drawbacks of this scheme are the large power dissipation, due to the large electrical resistivity of liquid lithium, and the need for very high current leads and contacts.…”

Section: Introductionmentioning

confidence: 99%

Innovative Design Option for Internal Coils

Bromberg

Tillack²

1991

Fusion Technology

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For shaping and control of tokamak plasmas it is desirable to have poloidal field coils as close as possible to the plasma.This implies poloidal field coils internal to the toroidal field system. Internal poloidal field coils made of single turn sections are proposed. Interconnects between the different sectors, based on liquid metal contacts, are discussed. The possibility of driving the current in the poloidal field coils by efficient MHD-induced currents (flows of conducting liquid metals across magnetic fields) is explored.

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The Integrated-Blanket-Coil Concept Applied to the Poloidal Field and Blanket Systems of a Tokamak Reactor

Cited by 16 publications

References 0 publications

Advanced tokamak reactors based on the spherical torus (ATR/ST). Preliminary design considerations

Advanced tokamak reactors based on the spherical torus (ATR/ST). Preliminary design considerations

The TITAN reversed-field-pinch fusion reactor study

Innovative Design Option for Internal Coils

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