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POLOIDAL FIELD SYSTEM FOR THE TOKAMAK PHYSICS EXPERIMENT



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437 IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY VOL 5 NO 2 JUNE 1995 POLOIDAL FIELD SYSTEM FOR THE TOKAMAK PHYSICS EXPERIMENT Joel H Schultz R D Pillsbury Jr A Radovinsky P W Wang Massachusetts Institute of Technology J Citrolo Princeton Plasma Physics Laboratory R J Bulmer D Lang T O Connor D Slack J Zbasnik Lawrence Livermore National Laboratory L Myatt Stone and Webster Abstract The Tokamak Physics Experiment TPX at Princeton will be the first tokamak with an all superconducting poloidal field PF magnet system The conductors are all cable in conduit CICC superconductors with a single conduit similar to those in the International Thermonuclear Experimental Reactor ITER 10 of the PF coils use Nb3Sn superconductor while 4 of them use NbTi High noise initiation and disruptions demand the use of an advanced quench detection system machine loads and requirements have necessitated changes in both the toroidal field TF and PF magnet systems 51 and an Engineering Change Proposal has been submttted This paper describes the ECP design A contract was awarded to complete preliminary design and R D of the PF system to an industrial team headed by Westinghouse Electric Corporation and including NorthrUp Grummanand Everson Electric I I INTRODUCTION ucond Lcond Bmaxaf mldtinitiation V sswing The Tokamak Physics Experiment TPX a steady state tokamak experiment to be built at the Princeton Plasma Physics Laboratory ll will be the first tokamak in the world with a superconducting poloidal field PF magnet system 2 All of the TPX magnets will use internally cooled cabled superconductors TPX will thus be an important precursor of ITER the Intemational Thermonuclear Experimental Reactor 3 Because the TPX mission includes steady state and extremely long pulse operation at full parameters the use of superconducting coils was an obvious choice for the magnet system The PF system has 14 coils 8 in a central solenoid CS stack and 6 outer PF coils providing 18 8 V s The TPX PF system will provide advanced shaping for doublenull high beta and high bootstrap fraction plasmas as well as single null plasmas at a full plasma current of 2 0 MA An isometric view of the TPX PF system is shown in Figure 1 tonnes 45 4 W 15 6 6 0 16 18 8 T TIS 0 11 REQuiREhiEms Parameter Units fcritical Tmareinheadroom bareinheadmom hI2R W m2 K hdisturbance Allowable Stress SM Figure 1 Isometric View of TPX PF System A conceptual magnet design was completed and reviewed CDR in 1993 141 Since then more detailed calculations of 300l600 1mNb3Sn bTi 600 2 3 yield 1 2 tensile 1 3 weld tensile Local Membrane PLocal Membrane 1 5 SM Bending l 5 SM Manuscript received Oct 17 1994 This work was supported by the US Department of Energy 1051 8223 95 04 00 K dlcc W m2 K Allowable 0 6 1 0 2 0 0 1995 IEEE 438 The coils are designed to remain superconducting and to recover without quench during all modes of normal operation



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