Фізика термоядерного синтезу та енергетики

☢️ Термоядерні реакції

DT reaction

D + T → ⁴He (3.5 MeV) + n (14.1 MeV). Cross section σ peak ~100 keV. Q-value = 17.6 MeV.

DD reactions

D + D → T (1.0 MeV) + p (3.0 MeV) or ³He (0.8 MeV) + n (2.5 MeV). Lower σ, harder.

Advanced fuels

D-³He, p-¹¹B. Lower neutron yields. Higher T required. Proton-boron: no neutrons.

Cross sections

σ(E): Maxwell-averaged. DT peak: ~100 keV. Thick-target yield: burn efficiency.

🔄 Lawson criterion

Ignition condition

nτ_E > 10²⁰ м⁻³·с для D-T. Triple product: nTτ_E > 3×10²¹ keV·м⁻³·с. Breakeven.

Temperature

T ≥ 10 keV (100 million K). Thermal equilibrium. Collisional plasma.

Confinement time

τ_E: energy confinement. H-mode enhancement H ~2-3. Scaling laws.

Break-even

Q = P_fusion/P_input. Q = 1: break-even. Q = 10: ignition. ITER goal.

⚡ Tokamaks

Toroidal geometry

Тороїдальні magnetic fields: B_тороїдальна + B_полудинна. Safety factor q. Plasma current I_p.

ITER

500 MW thermal, Q=10. R=6.2 m, B_т = 5.3 T. First plasma ~2035. International.

Magnetic confinement

β = plasma pressure / magnetic pressure. β_N ~ 3-4. β_limit ~ 5%.

Challenges

Disruptions, ELMs, instabilities, tritium. DEMO follow-up: commercial reactor.

🌊 Stellarators

НЕ symmetric

Тороїдальні non-axisymmetric. No plasma current. Steady state. Optimized coils.

W7-X

Wendelstein 7-X: operational Germany. Optimized magnetic field. Advanced stellarator.

Advantages

Steady state, no disruptions, stable. Geometric complexity: coil systems.

Future

Optimization: reduced neoclassical transport. 3D coils, computed-field shaping.

🔬 Plasma physics

MHD stability

Kink, tearing, ballooning modes. β-limit, q safety. Kink stabilization.

Transport

Neoclassical, turbulent. GyroBohm: scaling. Energy confinement τ_E.

Heating

ECRH (electron cyclotron), NBI (neutral beam), ICRH (ion cyclotron). Auxiliary, alpha particle.

H-mode

Pedestal, edge transport barrier. H ~2-3 enhancement. ELM mitigation.

🌊 Inertial confinement

Laser fusion

NIF (National Ignition Facility): 192 lasers, hohlraum, target compression. Yield.

Ignition

2022 NIF: Q > 1 achieved. 3.15 MJ yield > 2.05 MJ input. Burning plasma.

Challenges

Symmetry, robustness, efficiency. Target fabrication, repeatability.

Applications

Stockpile stewardship, high-energy physics. Inertial confinement energy.

📊 Графіки та діаграми

DT cross section

σ(E) vs E:

DT: highest σ among D reactions. Peak ~100 keV. Fusion power P ~ n²<σv>.

Lawson criterion

Triple product:

Confinement improvement needs. H-mode, optimized magnetic fields.

σ(E) peak ~ 100 keV Maxwell-averaged <σv> Effective at T ~ 10-20 keV Q-value: 17.6 MeV

🧪 Практичні приклади

Приклад 1: ITER

500 MW thermal, Q=10. 35 countries. First plasma ~2035. DEMO follow-up.

Приклад 2: NIF 2022

Ignition: Q > 1 achieved. 3.15 MJ yield > 2.05 MJ input. Burning plasma milestone.

Приклад 3: JET

European tokamak: Q_max ~ 0.67. D-T record. 59 MJ produced. H-mode optimization.

Приклад 4: W7-X

Stellarator: optimized B-field. Steady-state capable. Advanced helical coils.

© 2025 Науковий Симулятор. Всі права захищені.

Термоядерний синтез: зоряна енергія

Try it live

Everything above runs in your browser — open SPH Fluid and change the parameters while it is running. Nothing is installed, nothing is uploaded, the whole model lives in one tab.