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IAS-ZCF · Tritium purification

ZrCo Metal-Foam Tritium Purification, Getter and Storage Beds

Zirconium-cobalt alloy on an open-cell metal-foam support captures hydrogen isotopes from inert gas at room temperature and releases them on heating. Each bed is engineered to your gas, inventory and duty cycle.

ZrCo hydride (ZrCoH₃) Open-cell metal-foam support Price on quotation Updated September 2026

Quick answer

The IAS-ZCF series are tritium purification, getter and storage beds that use zirconium-cobalt (ZrCo) alloy supported on open-cell metal foam. ZrCo absorbs hydrogen isotopes (H, D, T) from inert carrier gas at room temperature, down to a plateau pressure of about 10⁻³ Pa, and releases them when heated. The metal foam spreads heat and holds the alloy in place. Each bed is engineered to the project and priced on quotation. Metal-hydride hydrogen-isotope purification systems are export-controlled nuclear dual-use items.

ZrCo metal-foam tritium purification bed (illustration)gas + T₂ / HT inpurified gas outheater / jacketZrCo on open-cell metal foam
Illustration only, not a product photograph.
ZrCoHydride-forming alloy (ZrCoH₃)
~10⁻³ PaAbsorption plateau at room temperature (literature)
Metal foamHeat transfer and alloy retention
Per projectSized to your gas and inventory

What a ZrCo purification bed does

Tritium systems need to pull hydrogen isotopes out of a gas stream, store them safely and deliver them again. Examples are a helium purge, a glovebox or process loop, or a fuel-cycle stream. ZrCo does this by chemistry rather than filtration. At room temperature the alloy absorbs H₂, D₂, T₂ and HT to form the hydride ZrCoH₃. Heating the bed later releases the gas for recovery, transfer or storage.

Why zirconium-cobalt

ZrCo was selected for the ITER tritium storage and delivery system as an alternative to depleted uranium. Published reviews give the reasons:

Known limitations, designed around: heated above about 573 K (300 °C) during desorption, ZrCo hydride can disproportionate into ZrH₂ and ZrCo₂ and lose capacity. Absorption is slower than uranium. Oxygen, nitrogen, water and carbon-bearing impurities can poison the alloy. Operating temperatures, regeneration procedure and gas pretreatment are set for each project accordingly.

Why a metal-foam support

A metal-hydride bed has two practical problems: heat (absorption is exothermic, desorption needs heat) and powder (hydride alloys break into fine particles over cycling). An open-cell metal foam matrix addresses both: its continuous metal ligaments conduct heat through the whole bed, and its cells hold the alloy in place with a uniform, low-resistance gas path. In a published comparison of small ZrCo beds, the copper-foam bed gave more uniform heating during desorption and removed absorption heat more effectively than a copper-fin bed.

Applications

For tritiated water (HTO), a ZrCo bed alone is not the answer. Detritiation systems usually combine catalytic oxidation with water adsorption, and getter beds handle elemental hydrogen isotopes.

Specifications: engineered per project

We do not publish one-size ratings, because capacity, flow and temperatures depend entirely on your gas and duty. Each proposal states these values for your bed:

ParameterHow it is set
Hydrogen-isotope capacity / ZrCo inventorySized to your inventory and cycle
Carrier gasTypically helium or argon; impurities reviewed per project
Gas flow and pressurePer project
Inlet and target outlet concentrationPer project
Absorption and regeneration temperaturesSet to limit ZrCo disproportionation
Foam matrix material and pore sizePer design
Vessel, containment and heatingPer design and applicable codes
Gas connections and leak rateVCR or welded; stated on quotation
InstrumentationTemperature, pressure; optional inlet/outlet tritium monitors

Monitoring the bed

Inlet and outlet tritium monitors show capture performance and early breakthrough. The all-metal, leak-tight IAS-TG30 and IAS-TG10 process monitors are built for this service. See tritium monitoring for fusion facilities for where beds and monitors fit in a fuel cycle.

Export control and end-use

Hydrogen-isotope storage or purification systems using metal hydrides are nuclear dual-use items under the Nuclear Suppliers Group guidelines. In the US Commerce Control List they fall under ECCN 1B231, "hydrogen isotope storage or hydrogen isotope purification systems using metal hydrides as the storage, or purification medium" (reason for control: nuclear nonproliferation). Every quotation therefore includes an end-use and end-user statement, and delivery depends on the export licenses required by the country of manufacture and, where applicable, the United States.

FAQ

What is a ZrCo tritium purification bed?

It is a sealed vessel filled with zirconium-cobalt (ZrCo) alloy that absorbs hydrogen isotopes (H₂, D₂, T₂, HT) from a gas stream at room temperature by forming a hydride (ZrCoH₃). The captured hydrogen isotopes are released later by heating the bed, so the bed can be used to clean a gas stream, or to store and deliver tritium.

Why ZrCo instead of uranium for tritium?

Uranium beds absorb hydrogen isotopes quickly but uranium is radioactive, pyrophoric and regulated as nuclear material. ZrCo is not radioactive, has low pyrophoricity, has a very low absorption plateau pressure at room temperature (about 10⁻³ Pa) and retains helium-3 from tritium decay well. That is why ZrCo was selected for the ITER tritium storage and delivery system.

Why put ZrCo on a metal foam?

Hydriding releases heat, and releasing hydrogen needs heat. Hydride powder also breaks down into fine particles over cycling. An open-cell metal foam spreads heat through the bed, holds the alloy in place and gives a uniform, low-resistance gas path. Published tests on ZrCo beds found a copper-foam bed gave more uniform heating during desorption and better removal of absorption heat than a copper-fin bed.

What gases can a ZrCo bed treat?

ZrCo beds are designed to capture hydrogen isotopes, typically from helium or argon carrier gas. Impurities such as oxygen, nitrogen, water vapor, CO, CO₂ and hydrocarbons can poison or consume the alloy, so the gas composition is reviewed for every project and upstream purification may be required. Tritiated water (HTO) is not captured by the ZrCo bed itself.

What are the limitations of ZrCo?

If ZrCo hydride is heated above about 573 K (300 °C) during hydrogen release, it can disproportionate into ZrH₂ and ZrCo₂, which lowers usable capacity over cycles. Its absorption is also slower than uranium. Bed design, operating temperature and regeneration procedure are set to manage these limits.

How much does a ZrCo tritium purification bed cost?

Every bed is sized to the project, so pricing is by quotation. Send the gas composition, flow, hydrogen-isotope inventory, target outlet concentration, pressure and end-use details, and we reply with a proposal, price, lead time and documentation list.

Is a ZrCo tritium purification bed export controlled?

Yes, in most cases. Hydrogen-isotope storage or purification systems using metal hydrides are nuclear dual-use items under the Nuclear Suppliers Group guidelines, and in the US they are listed under ECCN 1B231 (reason for control: nuclear nonproliferation). Shipments need the export licenses required by the country of manufacture and, for re-exports, by the US. An end-use and end-user statement is part of every quotation, and delivery depends on license approval.

How do I monitor a ZrCo bed?

Tritium monitors on the inlet and outlet show capture performance and breakthrough. The sealed, all-metal IAS-TG30 and IAS-TG10 process monitors are designed for this kind of process gas service.

Request a ZrCo purification bed proposal

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