Next-Step Spherical Torus Experiment and Spherical Torus Strategy in the Fusion Energy Development Path
Authors: M. Ono, M. Peng, C. Kessel, C. Neumeyer, J. Schmidt, J. Chrzanowski, D. Darrow, L. Grisham, P. Heitzenroeder, T. Jarboe, C. Jun, S. Kaye, J. Menard, R. Raman, T. Stevenson, M. Viola, J. Wilson, R. Woolley, and I. Zatz
Date of PPPL Report: October 2003
Puablished in: Nucear Fusion 44:3 (2004) 452-463
A spherical torus (ST) fusion energy development path which is complementary to proposed tokamak burning plasma experiments such as ITER is described. The ST strategy focuses on a compact Component Test Facility (CTF) and higher performance advanced regimes leading to more attractive DEMO and Power Plant scale reactors. To provide the physics basis for the CTF an intermediate step needs to be taken which we refer to as the "Next Step Spherical Torus" (NSST) device and examine in some detail herein. NSST is a "performance extension" (PE) stage ST with the plasma current of 5-10 MA, R = 1.5 m, and BT less than or equal to 2.7 T with flexible physics capability. The mission of NSST is to: (1) provide a sufficient physics basis for the design of CTF, (2) explore advanced operating scenarios with high bootstrap current fraction/high performance regimes, which can then be utilized by CTF, DEMO, and Power Plants, and (3) contribute to the general plasma/fusion science of high beta toroidal plasmas. The NSST facility is designed to utilize the Tokamak Fusion Test Reactor (or similar) site to minimize the cost and time required for the design and construction.