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Science & Technology of Controlled Fusion

A rigorous survey of confinement schemes, ignition criteria, and fuel cycles powering the commercial fusion race. Looking for breakthroughs and news? See the Science & Tech timeline.

Abstract

Controlled thermonuclear fusion requires confinement of a deuterium–tritium plasma above Ti1020 keVT_i \approx 10\text{--}20\ \text{keV} for durations sufficient to satisfy ignition. We summarize the dominant confinement architectures pursued by the global private sector and quantify their proximity to commercial viability.

§01

The Lawson Criterion & Triple Product

Self-sustaining ignition requires that the fusion power deposited in α-particles exceed plasma losses. Lawson's triple product expresses this as:

nτET    3×1021 m3skeVn\,\tau_E\,T \;\geq\; 3 \times 10^{21}\ \text{m}^{-3}\cdot\text{s}\cdot\text{keV}

where nn is ion density (m⁻³), τE\tau_E the energy confinement time (s), and TT the ion temperature (keV). For D-T fuel at T14 keVT \approx 14\ \text{keV}, ignition demands nτE1.5×1020 m3sn\tau_E \gtrsim 1.5 \times 10^{20}\ \text{m}^{-3}\,\text{s}.

Q=PfusionPinput,Q    ignitionQ = \frac{P_\text{fusion}}{P_\text{input}}, \quad Q \to \infty \iff \text{ignition}

JET (1997)

Q ≈ 0.67

NIF (2022)

Q ≈ 1.54

SPARC (2027 target)

Q ≥ 10

§02

Magnetic Confinement: Tokamaks & Stellarators

Magnetic confinement uses toroidal B\mathbf{B} fields to constrain charged particles along helical field lines, suppressing radial transport. The relevant pressure balance is governed by magnetic pressure:

Pmag=B22μ0P_\text{mag} = \frac{B^2}{2\mu_0}

The plasma beta — ratio of plasma to magnetic pressure — β=2μ0nkBTB2\beta = \dfrac{2\mu_0 n k_B T}{B^2} — sets the economic ceiling of any magnetic device. High-temperature superconducting (HTS) REBCO tapes enable B20 TB \approx 20\ \text{T}, shrinking reactor volume by roughly (B0/B)4(B_0/B)^4.

ArchitectureField TopologyLeading Device
Conventional TokamakAxisymmetric, induced toroidal currentITER, SPARC
Spherical TokamakLow aspect ratio, high βST40, STEP
Stellarator3D coil-shaped helical fieldW7-X, Stellaris
§03

Inertial Confinement: Laser-Driven Fusion

Inertial confinement fusion (ICF) compresses a cryogenic D-T pellet via MJ\sim\,\text{MJ}-class laser pulses, achieving densities ρ1000 g/cm3\rho \sim 1000\ \text{g/cm}^3. The relevant figure of merit is areal density:

ρR0.3 g/cm2\rho R \gtrsim 0.3\ \text{g/cm}^2

NIF's December 2022 ignition shot at LLNL deposited 2.05 MJ of UV laser energy onto a hohlraum and produced 3.15 MJ of fusion yield — the first lab demonstration of target energy gain Gtarget>1G_\text{target} > 1.

§04

Alternative Approaches: FRC, MTF, Z-Pinch

Field-reversed configurations (FRC) confine plasma in a self-organized compact toroid with zero toroidal field — pursued by TAE and Helion. Magnetized target fusion (MTF, General Fusion) and pulsed Z-pinch (Zap Energy) trade steady-state operation for pulsed compression cycles operating at 1–10 Hz.

§05

Fuel Cycles: D-T vs. Aneutronic

Deuterium-Tritium

2D+3T4He(3.5 MeV)+n(14.1 MeV)\,^2\text{D} + \,^3\text{T} \to \,^4\text{He}\,(3.5\ \text{MeV}) + n\,(14.1\ \text{MeV})

Highest cross-section at T15 keVT \sim 15\ \text{keV}; 80% energy carried by neutrons → activates structure; requires Li blanket for T breeding.

Aneutronic p-B11

p+11B34He+8.7 MeVp + \,^{11}\text{B} \to 3\,^4\text{He} + 8.7\ \text{MeV}

No primary neutrons; charged α-products enable direct-conversion electrostatic capture at η80%\eta \gtrsim 80\%. Requires T150 keVT \approx 150\ \text{keV}.

D-³He (Helion pathway)

2D+3He4He(3.6 MeV)+p(14.7 MeV)\,^2\text{D} + \,^3\text{He} \to \,^4\text{He}\,(3.6\ \text{MeV}) + p\,(14.7\ \text{MeV})

Aneutronic primary reaction; ³He sourced via D-D side-channel breeding. Charged products permit pulsed direct-conversion via Faraday induction.

Citations & Sources

Academic & financial rigor
  1. [01]

    Lawson, J. D. — Some Criteria for a Power Producing Thermonuclear Reactor

    Proc. Phys. Soc. B 70 (1957)

  2. [02]

    Indirect Drive ICF Ignition at the National Ignition Facility

    Phys. Rev. Lett. 132, 065102 (2024)

  3. [03]

    SPARC: A High-Field, Compact, Net-Energy DT Tokamak

    J. Plasma Phys. 86 (2020) — Creely et al.

  4. [04]

    Operation of the Stellarator Wendelstein 7-X

    Nature Communications (2024)

  5. [05]

    ITER Research Plan Within the Staged Approach

    ITER Organization Tech. Report (2018)

  6. [06]

    Helion Polaris Performance Disclosure

    Helion Energy Technical Brief, 2025

  7. [07]

    REBCO HTS Magnet Performance for Compact Fusion

    Nature Energy (2021) — CFS / MIT PSFC

  8. [08]

    Aneutronic Fusion and Direct Energy Conversion

    Fusion Sci. Tech. (Rider, 1995)