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Greenwald Density Limit Plasma Calculator physics
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Greenwald Density Limit Plasma Calculator

Tokamak Magnetic Confinement: Evaluate the empirical Greenwald density limit ($n_G = I_p / (\pi a^2)$), operational density fraction ($n_e/n_G$), and plasma disruption safety margin.

Tokamak Geometry & Plasma Current

Density Limit & Stability Metrics

Greenwald Limit n_G
-- ×10¹⁹ m⁻³
Greenwald Fraction f_G
--
Cylindrical q_cyl
--
Murakami Number M
--
Disruption Margin
-- %
Stability Regime
STABLE

The Greenwald Limit & Tokamak Operational Boundaries

In magnetic confinement fusion, achieving high fusion power requires maximizing fuel density ($P_{fus} \propto n_i^2$). However, tokamak density is constrained by magnetohydrodynamic (MHD) and radiative limits.

1. Mathematical Formulation

n_G = I_p / (π · a²)   [10²⁰ m⁻³]
f_G = n̄_e / n_G         [Greenwald Fraction]
q_cyl = (5 · a² · B_T) / (R₀ · I_p) · ((1 + κ²) / 2)

2. Key Regimes

Frequently Asked Questions

What is the Greenwald density limit in tokamak physics?

The Greenwald density limit is an empirical upper bound on the line-averaged electron density in tokamaks: $n_G = I_p / (\pi a^2)$ [expressed in units of $10^{20}\,\text{m}^{-3}$, with plasma current $I_p$ in $\text{MA}$ and minor radius $a$ in $\text{m}$]. Discovered by Martin Greenwald in 1988, attempting to operate standard unpelletized H-mode or L-mode plasmas above $f_G = n_e / n_G > 1.0$ triggers intense edge radiation (Marfes), magnetic tearing modes ($m/n = 2/1$), and catastrophic plasma disruptions.

Can advanced tokamaks exceed the Greenwald limit?

Yes. Cryogenic core pellet injection (high-field-side launch) and central neutral beam fueling can deposit fuel deep inside the magnetic core without swelling the scrape-off layer (SOL) edge density. Tokamaks like DIII-D, ASDEX Upgrade, and EAST have sustained peaking factors enabling $n_e/n_G \approx 1.2\sim 1.5$ while maintaining an edge density safely below the disruptive boundary.

Why does exceeding the Greenwald limit cause a plasma disruption?

At high edge electron densities, atomic impurity radiation (carbon, tungsten, beryllium) exceeds the local ohmic and auxiliary heating input power in the edge plasma. This cools the edge, shrinking the current profile and steepening the radial current gradient $dj/dr$ near the $q=2$ rational flux surface. The resulting resistive tearing mode grows rapidly, locking to the wall and triggering a thermal quench followed by a vertical displacement event (VDE).