Zircaloy 4 • UNS R60804

Zircaloy 4 is a zirconium-based alloy renowned for its exceptional corrosion resistance, mechanical strength, and heat transfer properties. It is primarily used in nuclear power applications, specifically as cladding material for fuel rods in nuclear reactors..

Zircaloy 4 is highly valued for its ability to withstand the demanding conditions of nuclear reactors, including high temperatures, radiation exposure, and corrosive environments.

Zircaloy 4 demonstrates excellent resistance to corrosion in high temperature water and steam environments, making it an ideal choice for nuclear reactors. The alloy also exhibits good resistance
to general corrosion, including acids, alkalis, and saltwater. It is particularly renowned for its superior resistance to stress corrosion cracking, which is crucial for maintaining the integrity of nuclear
fuel cladding.

The primary application of Zircaloy 4 is in the nuclear power industry, where it is widely used as cladding material for fuel rods in pressurized water reactors (PWRs) and boiling water reactors (BWRs). It provides a protective barrier around the nuclear fuel, preventing the release of radioactive materials and ensuring thesafety and efficiency of the reactor.

Available tube product forms

Typical Applications

Typical Manufacturing Specifications

  • ASTM B353
  • ASTM B352
  • Also individual customer specifications

Industries predominantly using this grade


Technical Data

Mechanical Properties


Tensile Strength 550 MPa (80,000 psi) minimum
Yield Strength 380 MPa (55,000 psi) minimum
Elongation 20% minimum (in 2-inch gauge length)
Hardness HRB 80-90 (Typical)

Physical Properties


Density 6.51 g/cm³
Melting Range 1852°C (3366°F)
Thermal Conductivity 22.3 W/m·K (at 20°C)
Electrical Resistivity 42.0 μΩ·m (at 20°C)
Modulus of Elasticity 99 GPa (14.4 x 10^6 psi)

Chemical Composition (% by weight)


Element Min Max
Zr - 98.8
Sn 1.2
1.7
Fe -
0.2
Cr 0.7
0.13
Ni -
0.1
O -
0.18
H -
0.005