2006 48th Annual Meeting of the Division of Plasma Physics
Monday–Friday, October 30–November 3 2006;
Philadelphia, Pennsylvania
Session UI1: Plasma Technology: Magnetic Confinement
9:30 AM–12:30 PM,
Thursday, November 2, 2006
Philadelphia Marriott Downtown
Room: Grand Salon ABF
Chair: Dick Majeski, Princeton Plasma Physics Laboratory
Abstract ID: BAPS.2006.DPP.UI1.4
Abstract: UI1.00004 : Ignited Spherical Tokamaks as a Reactor Development Facility*
11:00 AM–11:30 AM
Preview Abstract
Abstract
Author:
Leonid Zakharov
(Princeton University, PPPL)
The talk presents the concept of Ignited Spherical Tokamaks
(IST), which
can serve as a neutron fusion source for the Reactor Development
Facility. The IST would be uniquely consistent with three
objectives of
magnetic
fusion, i.e., (a) high power density plasma regime (5-10
MW/m$^3$), and
high neutron flux (b) for designing the ``first wall'' of the
reactor (up
to the fluence of 15 MW year/m$^2$), and (c) for developing the
tritium cycle.
The lithium-based plasma facing components (LiWalls) of an IST
provide
the pumping boundary conditions for the plasma. When combined
with central
fueling of the plasma by low energy (E=45-50 keV) neutral beam
injection
(NBI), the LiWall environment leads to a flat plasma temperature
T=E/3. This results in a super-critical ignition regime, with
ion-temperature
gradient turbulence eliminated, when the energy confinement is
close to
neo-classical, while the high current density at the separatrix
robustly
stabilizes the edge-localized modes.
Unlike conventional approach to magnetic fusion, the super-critical
ignition regime relies on core fueling by NBI and fast expulsion
of the
$\alpha$-particles, rather than on their heating the plasma. In this
regards, the IST configuration (for the neutron source purposes) and
stellarators (as power reactors), rather than tokamaks, have
similarity regarding super-critical ignition regime.
A separate national program ($\simeq$\$2-2.5 B for $\simeq$ 15
years) can
realistically develop an Ignited Spherical Tokamak as a fusion
neutron source for reactor R\&D in 3 steps (two with DD, and one
with DT plasmas), i.e.,
\begin{enumerate}
\item A spherical tokamak, targeting achievement of absorbing wall
regime with neo-classical confinement in a DD plasma and
$Q_{DT-equiv}=1$,
\item Full scale DD-prototype of IST for demonstration of all
aspects of
stationary super-critical regime with $Q_{DT-equiv}\simeq50$.
\item IST itself with a DT plasma and $Q_{DT}\simeq50$ for reactor
technology and $\alpha$-particle power extraction studies.
\end{enumerate}
*This work is supported by US DoE contract No.\ DE--AC020--76--CHO--3073
To cite this abstract, use the following reference: http://meetings.aps.org/link/BAPS.2006.DPP.UI1.4