Zirconium UNS R60704 Round Bar

Zirconium Rod is a cylindrical metal bar known for its exceptional corrosion resistance and high-temperature stability, widely used in aerospace, chemical processing, and medical implant applications.

 

UNS R60704, also called Zircadyne 704, is a standout zirconium alloy known for its balanced composition and exceptional performance. UNS R60704 is renowned for its high strength, excellent corrosion resistance, and thermal stability.

 

Size	Dia.: 5 mm - 400 mm
Material	R60702, R60704, R60705
Standard	ASTM B550, ASTM B351
Surface	Black, pickling, sand-blasting, polished
Condition	Cold rolled(Y), hot rolled(R), annealed (M), quenching (C)
Shape	Square rod, round rod, hexagonal rod.

 

Chemical Composition of Zirconium Rod

Grade	Element Composition (%) <
	Zr+Hf	Hf	Fe+Cr	Sn	H	N	C	Nb	O
R60702	99.2	4.5	0.2	--	0.005	0.025	0.05	--	0.16
R60704	97.5	4.5	0.20~0.40	1.0~2.0	0.005	0.025	0.05	--	0.18
R60705	95.5	4.5	0.2	--	0.005	0.025	0.05	2.0~3.0	0.18

Mechanical Properties of Zirconium Rod

Material	State	Rm (≥)/MPa	Rp0.2 (≥)/MPa	A50mm (≥)/%
Zirconium 702	Annealed	379	207	16
(UNS R60702)
Zirconium 704	Annealed	413	241	14
(UNS R60704)
Zirconium 705	Annealed	552	379	16
(UNS R60705)

Why UNS R60704 is Essential in Nuclear Reactors

UNS R60704 is an ideal choice for nuclear reactors because of its outstanding performance under high temperatures and aggressive environments. The alloy's low thermal neutron absorption ensures efficient neutron economy, which is essential for sustaining chain reactions in reactor cores. This property plays a crucial role in the efficient operation of nuclear reactors.

In addition, UNS R60704 provides excellent corrosion resistance to steam and water, which are common in reactor cooling systems. This ability to resist corrosion helps prolong the service life of components exposed to extreme conditions.

Furthermore, UNS R60704 offers excellent mechanical strength, ductility, and thermal conductivity, which ensures both the structural integrity of reactor components and effective heat transfer. The alloy's radiation stability further enhances its performance, making it a reliable option for fuel cladding and other critical reactor components.

Differences Between UNS R60704 and Zircaloy-4

While Zircaloy-4 and UNS R60704 are both widely used in nuclear applications, there are key differences that make each alloy suitable for specific uses. UNS R60704 has a wider range of tin content (1.0 to 2.0%) and includes additional elements like chromium (0.2 to 0.4%) and iron (0.2 to 0.4%), which contribute to its superior performance in high-corrosion environments.

Zircaloy-4, on the other hand, has a more controlled composition, with 1.5% tin, 0.2% iron, and 0.1% chromium. This makes Zircaloy-4 better suited for fuel cladding, as it exhibits higher tensile strength, greater elongation, and lower hydrogen uptake, which is critical for the integrity of the cladding in reactor conditions.

While UNS R60704 provides excellent corrosion resistance and mechanical stability in a range of high-temperature applications, Zircaloy-4 is more tailored to the specific needs of nuclear fuel cladding.

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