Mechanical properties of zirconium 60702 plate: Why is it the preferred material for the nuclear industry?
As a key material for nuclear reactor fuel cladding, the mechanical properties of zirconium alloy 60702 (Zirconium 60702) are directly related to the safety and service life of nuclear facilities. This article will deeply analyze the strength, hardness, ductility, and fatigue properties of zirconium 60702 plate, and provide authoritative test data to help you fully understand the mechanical performance of this special alloy.
1. Key mechanical properties of zirconium 60702 plate (ASTM B551 standard)
1.1 Basic mechanical parameters (room temperature)
| Performance index | Annealed state (O) | Cold worked state (H) | Test standard |
| Tensile strength (MPa) | 380-520 | 520-680 | ASTM E8 |
| Yield strength (MPa) | 170-240 | 340-480 | ASTM E8 |
| Elongation (%) | ≥16 | ≥10 | ASTM E8 |
| Hardness (HV) | 120-160 | 160-220 | ASTM E92 |
| Elastic modulus (GPa) | 99 | 99 | ASTM E111 |
Note: Data is based on 2-20mm thick plates, and the test direction is the rolling direction
1.2 High temperature performance (300℃ water environment)
- Tensile strength: decreased by about 15-20%
- Yield strength: decreased by about 25-30%
- Creep resistance: significantly better than ordinary zirconium alloys
2. 4 Key Factors Affecting Mechanical Properties
2.1 Heat treatment state
Annealed state (O):
Better ductility (elongation ≥ 16%)
Suitable for deep stamping
Cold worked state (H):
Higher strength (tensile strength can reach 680MPa)
For parts requiring high stiffness
2.2 Microstructure
Grain size: ASTM 6-8 is the best
Texture orientation: affects anisotropic properties
2.3 Chemical composition fluctuations
Increase in Sn content → strength ↑, ductility ↓
O content increases → strength ↑, toughness ↓
2.4 Processing technology
Rolling deformation control
Final annealing temperature (usually 550-650℃)
3. Comparison of mechanical properties with other zirconium alloys
| Alloy grade | Tensile strength (MPa) | Yield strength (MPa) | Elongation (%) | Main applications |
| 60702 | 380-520 | 170-240 | ≥16 | Nuclear fuel cladding |
| 702 | 340-440 | 170-210 | ≥20 | Chemical equipment |
| 705 | 550-750 | 480-620 | ≥12 | Structural components |
60702 achieves the best balance between strength and ductility
4. Mechanical properties test methods
4.1 Standard test process
Tensile test (ASTM E8)
Specimen specifications: GB/T 228.1 standard specimen
Strain rate: 0.005-0.01/min
Hardness test (ASTM E92)
Vickers hardness HV1 load
Impact test (ASTM E23)
Charpy V-notch specimen
4.2 Special tests
High temperature creep test (ASTM E139)
Determination of hydride orientation factor (exclusive for nuclear grade materials)
5. FAQ
Q: Why does nuclear grade zirconium alloy need to control anisotropy?
A: Excessive anisotropy will lead to uneven irradiation growth and affect the dimensional stability of the cladding tube.
Q: Can cold-worked plates be used for welded structures?
A: It is recommended to anneal before welding, otherwise, cracks are likely to occur.
Q: How to improve the fatigue performance of zirconium alloys?
A: By controlling the grain size (ASTM 7-8 grade) and surface finish (Ra≤0.8μm).
6. Conclusion: Mechanical properties determine application reliability
The excellent mechanical properties of the zirconium 60702 plate make it:
The preferred material for nuclear fuel cladding
Ideal for high-temperature corrosion-resistant components
Precision applications requiring strength-toughness balance
Need professional technical support? Contact us to obtain a complete mechanical properties of zirconium alloy 60702 test report template. Email:linhui@lhtitanium.com
