The Fusion Record — Fusion Energy News ← Home · Knowledge base
Fuels & Materials

Tungsten as a Divertor Material

Why tungsten is the leading material for fusion reactor divertors — with the highest melting point of any element, low sputtering, and low tritium retention, but challenged by neutron-induced embrittlement.

Reviewed Last reviewed: 9 Aug 2026 · Category: Fuels & Materials

Why Tungsten?

Tungsten (W) is the primary candidate material for divertor plasma-facing components in fusion reactors due to its extraordinary properties: the highest melting point of any element (3,422°C), very low sputtering yield under hydrogen isotope bombardment, low tritium retention, and high thermal conductivity. These properties make it uniquely suited to withstand the extreme heat fluxes (10–20 MW/m²) at the divertor strike points.[1]

ITER divertor: ITER’s divertor uses 54 cassettes, each containing tungsten monoblocks bonded to copper-alloy cooling tubes. The total tungsten mass exceeds 100 tonnes. Each monoblock is a small tile (~28×22×12 mm) with a drilled hole for the cooling tube, manufactured to extremely tight tolerances.

Challenges

Neutron embrittlement: Under fusion neutron irradiation, tungsten’s ductile-to-brittle transition temperature (DBTT) rises dramatically, potentially above operating temperature, making it prone to cracking. Recrystallisation: At temperatures above ~1,200°C (achievable during transients), tungsten recrystallises and loses its engineered mechanical properties. Melting: During disruptions or giant ELMs, surface temperatures can briefly exceed tungsten’s melting point.[2]

Advanced Concepts

Research on tungsten alloys (W-Re, W-TiC, W-Y2O3), tungsten fibre-reinforced tungsten composites (Wf/W), and self-passivating tungsten alloys (W-Cr-Y) aims to improve ductility and oxidation resistance beyond what pure tungsten can offer.[3]

Sources

  1. Rieth, M. et al. "Recent progress in research on tungsten materials for nuclear fusion applications in Europe." Journal of Nuclear Materials, 432, 482–500, 2013.
  2. Pitts, R.A. et al. "A full tungsten divertor for ITER." Journal of Nuclear Materials, 438, S48–S56, 2013.
  3. Linsmeier, Ch. et al. "Development of advanced first wall and blanket materials for a fusion power plant." Nuclear Fusion, 57, 092007, 2017.

Related