Bar and Rod
Plate and Sheet
Strip
Pipe and Tube
Wire
Welding
Powder Material
Cast Products
Forged Products
Fittings
Fastening
Round Bar:
φ2–500 mm, 1–6 m length
Flat/Square Bar:
4–100 mm thickness/width
Hex Bar:
A/F 3–100 mm
Hollow Bar:
OD 20–300 mm
Sheet:
0.3–6 mm thickness
Medium Plate:
6–25 mm thickness
Heavy Plate:
25–100 mm thickness
Standard Strip:
0.05–3 mm thick,
10–600 mm wide
Precision strip:
0.01–0.5 mm thick,
tight tolerance ±0.005 mm
Foil:
0.005–0.1 mm thick
Seamless Tube:
OD 6–450 mm,
WT 1–50 mm,
1–12 m length
Welded Tube:
OD 10–600 mm,
WT 1–20 mm
Capillary Tube:
OD 1–10 mm,
WT 0.1–2 mm
Wire Form:
Cold Drawn Wire,
Bright Wire,
Spring Wire,
Fine Wire,
Ultra-fine Wire
General Diameter:
φ0.1–10 mm
Coil Weight:
50–500 kg,
customizable tolerance
Solid Wire:
φ0.8–4.0 mm
Flux-cored Wire:
φ1.2–4.0 mm
Welding Rod:
φ2.0–5.0 mm
Powder Form:
AM 3D Printing Powder,
Spherical Powder,
Gas-atomized Powder,
Water-atomized Powder
Particle Size:
10–150 μm
Sphericity:
≥90% for AM grade
Cast Ingot:
φ200–800 mm
Precision Casting:
min wall 0.5 mm
Cast Pipe:
OD 100–600 mm,
WT 10–50 mm
Forged Bar:
Φ35–500 mm
Forged Ring:
OD 200–2000 mm
Forging Weight:
1–5000 kg
Fittings Form:
Elbow, Tee, Reducer, Flange, Cap, Outlet, Lap Joint
Size range:
1/2''–24'' (DN15–DN600)
Wall thickness:
Sch10–Sch160, STD, XS, XXS
Pressure Class:
150–2500 LB
Fastening Form:
Bolt, Nut, Screw, Stud, Washer, Pin, Rivet
Metric: M3–M64
Imperial: #4–2.5''
Length: 6–500 mm
R60804 is Zircaloy-4 (Zr-1.5Sn-Fe-Cr), a nuclear-grade zirconium alloy. This datasheet presents the material within the American (ASTM / ASME / UNS) standard system.
Zirconium nuclear alloys combine a very low thermal-neutron-capture cross-section with good corrosion resistance in high-temperature reactor water and steam. R60804 is Zircaloy-4 (Zr-1.5Sn-Fe-Cr); the tin, iron and chromium (and, in Zircaloy-2, nickel) additions improve corrosion resistance and strength while the controlled low hafnium content preserves neutron economy. It is used principally as fuel cladding and core structural material in pressurised-water reactors (PWR), and is supplied in the annealed condition.
Typical applications include pressurised-water-reactor (PWR) fuel cladding and core structural components.
| Property | Value | Unit |
|---|---|---|
| Density | 6.51 | g/cm³ |
| Melting point | 1852 | °C |
| Elastic modulus | 99 | GPa |
| Coefficient of thermal expansion (20–100 °C) | 5.9 | µm/m·°C |
| Thermal conductivity (20 °C) | 22 | W/m·K |
| Specific heat (20 °C) | 285 | J/kg·K |
| Structure | Hexagonal close-packed (alpha) | — |
| Element | Symbol | Min % | Max % | Role in Alloy |
|---|---|---|---|---|
| Zirconium | Zr | Balance | — | Base element |
| Tin | Sn | 1.20 | 1.70 | Strength, corrosion resistance |
| Iron | Fe | 0.18 | 0.24 | Corrosion resistance |
| Chromium | Cr | 0.07 | 0.13 | Corrosion resistance |
| Oxygen | O | — | 0.16 | Interstitial; strength |
| Nickel | Ni | — | 0.007 | Restricted (Zircaloy-4) |
| Hafnium | Hf | — | 0.010 | Controlled low (nuclear) |
Annealed condition, typical values for ASTM B350 UNS R60804.
| Condition | Property | Value |
|---|---|---|
| Annealed | Tensile strength (UTS) | ≥413 MPa (60 ksi) |
| Annealed | 0.2% yield strength | ≥241 MPa (35 ksi) |
| Annealed | Elongation at break | ≥16 % |
| Cold-worked | Tensile strength (UTS) | higher; less ductile |
| — | Elastic modulus | 99 GPa |
Confirm against the mill test report. Strength depends on oxygen content and condition.
| Environment | Performance | Notes |
|---|---|---|
| Reactor coolant water / steam | Excellent | Low corrosion + low neutron capture |
| High-temperature water (288–360 °C) | Excellent | Fuel-cladding service |
| Sulfuric acid (≤70%) | Excellent | Resistant; attacked at high conc. |
| Strong alkalis | Excellent | Resists hot caustic |
| Ferric / cupric chlorides, aqua regia | Poor | Attacked; also HF |
Zirconium offers outstanding resistance to hydrochloric and nitric acids, hot caustic and many organic acids through a self-healing oxide film, but is attacked by hydrofluoric acid, ferric and cupric chlorides, wet chlorine and aqua regia.
A reactive metal; not hardenable by precipitation. Properties are governed by working and annealing.
Anneal Anneal in vacuum or a protective atmosphere at approximately 540–815 °C to recrystallise and restore ductility after cold work. Avoid oxygen, nitrogen and hydrogen pickup, which embrittle the metal; pickling removes surface contamination.
Excellent weldability by inert-gas processes; the weld and hot metal must be fully shielded from air (trailing shields, backing gas or chambers), because oxygen, nitrogen and hydrogen pickup cause embrittlement.
| Welding Process | Applicability | Notes |
|---|---|---|
| GTAW / TIG | Excellent | Full inert shielding / trailing shield |
| GMAW / MIG | Good | Matching filler |
| EBW / plasma | Good | Vacuum or high-purity shielding |
Weld under full inert-gas shielding with clean surfaces; a bright, silvery weld indicates good shielding, while colours indicate contamination.
Machining Guidelines
| Parameter | Recommendation |
|---|---|
| Machinability | Fair; sharp tooling, slow speeds, heavy feeds |
| Caution | Fine chips/dust are pyrophoric — manage swarf, flood coolant |
| Coolant | Ample non-chlorinated coolant |
Forming Processes
| Process | Notes |
|---|---|
| Cold forming | Good; ductile when annealed |
| Hot forming | Performed warm/hot under protection from oxidation |
| Industry | Typical Components | Key Requirements |
|---|---|---|
| Nuclear fuel | Fuel-rod cladding tubes | Low neutron capture + corrosion resistance |
| Reactor core | Structural grids, channels | Strength + corrosion in coolant |
| pressurised-water reactors (PWR) | Core components | Neutron economy + durability |
| Power generation | Reactor internals | High-temperature water resistance |
| Product Form | ASTM Standard | Notes |
|---|---|---|
| Strip, sheet and plate | ASTM B352 | UNS R60804 |
| Bar and wire | ASTM B351 | UNS R60804 |
| Seamless and welded tube (cladding) | ASTM B353 | UNS R60804 |
| Material designation | UNS R60804 | Zircaloy-4 (Zr-1.5Sn-Fe-Cr) |
Zircaloy-4 (Zircaloy-4 (Zr-1.5Sn-Fe-Cr)). UNS R60804.
| UNS | Composition | Grade | Best Used For |
|---|---|---|---|
| R60804 | Zircaloy-4 (Zr-Sn-Fe-Cr) | Nuclear | PWR fuel cladding and core structural material |
| R60802 | Zircaloy-2 (Zr-Sn-Fe-Cr-Ni) | Nuclear | BWR fuel cladding (with nickel) |
| R60001 | Nuclear-grade Zr | Nuclear | Nuclear-grade unalloyed zirconium |
| R60702 | Unalloyed Zr | Industrial | Industrial zirconium; chemical service |
| R60705 | Zr-2.5Nb | Industrial | Higher-strength zirconium-niobium alloy |
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