Fusion core start-up, ignition and burn simulations of reversed-field pinch (RFP) reactors

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A transient reactor simulation model is developed to investigate and simulate the start-up, ignition and burn of a reversed-field pinch reactor. The simulation is based upon a spatially averaged plasma balance model with field profiles obtained from MHD quasi-equilibrium analysis. Alpha particle heating is estimated from Fokker-Planck calculations. The instantaneous plasma current is derived from a self-consistent circuit analysis for plasma/coil/eddy current interactions. The simulation code is applied to the TITAN RFP reactor design which features a compact, high-power-density reversed-field pinch fusion system. A contour analysis is performed using the steady-state global plasma balance. The results are presented with contours ... continued below

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Pages: 166

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Chu, Yuh-Yi January 1, 1988.

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Description

A transient reactor simulation model is developed to investigate and simulate the start-up, ignition and burn of a reversed-field pinch reactor. The simulation is based upon a spatially averaged plasma balance model with field profiles obtained from MHD quasi-equilibrium analysis. Alpha particle heating is estimated from Fokker-Planck calculations. The instantaneous plasma current is derived from a self-consistent circuit analysis for plasma/coil/eddy current interactions. The simulation code is applied to the TITAN RFP reactor design which features a compact, high-power-density reversed-field pinch fusion system. A contour analysis is performed using the steady-state global plasma balance. The results are presented with contours of constant plasma current. A saddle point is identified in the contour plot which determines the minimum value of plasma current required to achieve ignition. An optimized start-up to ignition and burn path can be obtained by passing through the saddle point. The simulation code is used to study and optimize the start-up scenario. In the simulations of the TITAN RFP reactor, the OH-driven superconducting EF coils are found to deviate from the required equilibrium values as the induced plasma current increases. This results in the modification of superconducting EF coils and the addition of a set of EF trim coils. The design of the EF coil system is performed with the simulation code subject to the optimization of trim-coil power and current. In addition, the trim-coil design is subject to the constraints of vertical-field stability index and maintenance access. A power crowbar is also needed to prevent the superconducting EF coils from generating excessive vertical field. A set of basic results from the simulation of TITAN RFP reactor yield a picture of RFP plasma operation in a reactor. Investigations of eddy current are also presented. 145 refs., 37 figs., 2 tabs.

Physical Description

Pages: 166

Notes

NTIS, PC A08/MF A01; 1.

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  • Other Information: Thesis (Ph.D.). Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted

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  • Other: DE88006606
  • Report No.: UCLA/PPG-1128
  • Grant Number: FG03-86ER52126
  • DOI: 10.2172/5386865 | External Link
  • Office of Scientific & Technical Information Report Number: 5386865
  • Archival Resource Key: ark:/67531/metadc1070275

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Creation Date

  • January 1, 1988

Added to The UNT Digital Library

  • Feb. 4, 2018, 10:51 a.m.

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  • March 29, 2018, 1:09 p.m.

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Chu, Yuh-Yi. Fusion core start-up, ignition and burn simulations of reversed-field pinch (RFP) reactors, report, January 1, 1988; United States. (digital.library.unt.edu/ark:/67531/metadc1070275/: accessed June 24, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.