ASTM B550Zr-4 nuclear-grade zirconium crucible 30ml

Nuclear-grade zirconium crucibles are made of low-hafnium, high-purity nuclear-grade zirconium/zirconium alloy, strictly adhering to ASTM B550 and GB/T 26314 nuclear zirconium material specifications. The hafnium content is controlled to <0.01% (a core indicator for nuclear-grade materials; industrial zirconium hafnium content is at most 2%, making it unsuitable for nuclear applications).

Comparison table of chemical composition of zircon crucibles：

Comparison table of mechanical properties of zirconium crucibles：

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Core Physicochemical Properties (Unique Advantages for Nuclear Operation)

1. Extremely Low Neutron Absorption Cross Section

Zirconium's thermal neutron capture cross section is far lower than that of titanium, molybdenum, stainless steel, and graphite. It does not absorb neutrons and inhibit nuclear reactions, making it the only high-temperature crucible substrate suitable for nuclear fuel and irradiation experiments.

2. Ultra-High Temperature Stability

Melting point 1852℃, long-term stable operating temperature ≤1700℃; low coefficient of linear expansion, strong thermal shock resistance, no cracking or deformation even after repeated temperature rises and falls.

3. Ultimate Chemical Inertness + Radiation Corrosion Resistance

Surface self-passivation The ZrO₂ protective film is resistant to concentrated nitric acid, strong alkalis, molten uranium oxide, rare earth molten salts, and radioactive waste liquids; it does not undergo solid-phase reactions with uranium, plutonium, rare earth, or zirconium alloy melts at high temperatures, preventing material contamination; only hydrofluoric acid systems cause slight corrosion.

4. Irradiation Stable, No Activation Impurities

The high-purity formula produces fewer activation products and has a shorter half-life after irradiation, facilitating post-processing of nuclear waste; it prevents carbon contamination from graphite crucibles and silicon impurity precipitation from alumina crucibles.

5. Mechanical and Processing Properties

Density 6.51 g/cm³, moderate weight for easy transport; forgeable, spin-formed, and precision CNC machined with a dimensional tolerance of ±0.1 mm; inner wall mirror polishing Ra≤0.2 μm; molten material does not stick to the wall, discharges completely, and is easy to clean.

Key Differences Between Nuclear-Grade Zircon Crucibles and Ordinary Industrial Zirconium Crucibles

II. Core Application Areas

(I) Nuclear Fuel Cycle (Largest Application Scenario)

Uranium-Based Nuclear Fuel Preparation
Uranium oxide (UO₂), uranium fluoride, uranium metal vacuum melting, co-precipitation calcination, gel microsphere granulation; zirconium crucibles prevent the introduction of impurities, ensuring fuel pellet purity and avoiding impurities that reduce reactor thermal efficiency and cause irradiation defects;
Zirconium Alloy Cladding Raw Material Melting
Vacuum induction melting of Zr-4 and Zr-2.5Nb fuel cladding tubing billets; high-temperature molten zirconium-tin and zirconium-niobium alloy special containers, eliminating carbon and silicon contamination, ensuring cladding corrosion resistance and irradiation life;
Spent Fuel Dry Reprocessing
High-temperature chlorination volatilization and oxidation volatilization processes; bearing irradiated spent fuel blocks, resistant to radioactive molten salts and high-temperature oxidizing media, and resistant to strong radioactive corrosion.

(II) Isotope Production and Nuclear Research Laboratory
Medical/Industrial Isotope Preparation
High-temperature synthesis and melting separation of radioactive isotopes such as cobalt, strontium, iodine, and lutetium; low neutron absorption does not deplete the neutron flux of the target; high-purity materials ensure the radioactive purity of the isotopes and reduce interference from impurities in the detection results;
Reactor Irradiation Sample Carrier
High-temperature irradiation experimental crucibles inside the reactor core, used for high-temperature sintering of irradiated materials and nuclear targets; thermally shock resistant, can directly enter and exit the high-temperature loop of the reactor core;
Nuclear Analysis and Radiochemical Digestion
Alkali/acid melting digestion of radioactive ores, nuclear waste, and radioactive soil samples, replacing platinum crucibles, lower cost, resistant to strong molten alkalis, and without the risk of platinum alloying with radioactive melts.

(III) Radioactive Waste Treatment
High-Level Radioactive Waste Vitrification
Borosilicate glass is used as a high-temperature melting carrier for nuclear waste, resistant to radioactive molten waste containing cesium, strontium, and plutonium. It does not leach heavy metals or radionuclides at high temperatures, and the stability of the solidified body meets geological disposal standards.
Nuclear Waste Ceramic Solidification
Titanium-zirconium-based ceramic solidification bodies are sintered at high temperatures to carry radioactive nuclide solid solution precursors, ensuring the purity of the solidified crystal lattice.

(IV) Specialized Nuclear Metallurgy (Extended Applications)
* Nuclear-grade Rare Metal Smelting
* Vacuum remelting of hafnium, tantalum, niobium, rare earth elements, and high-purity zirconium; zirconium's chemical inertness prevents it from reacting with active metals, enabling the preparation of impurity-free nuclear targets and reactor structural components;
* Neutron Absorption/Shielding Material Development
* High-temperature sintering crucibles for boride and rare earth neutron-absorbing alloys, preventing the crucible material from altering the alloy's neutron absorption performance;
* Fusion/Advanced Nuclear Energy Development
* High-temperature preparation of tokamak-related tritium breeding materials and liquid metal targets, adaptable to vacuum, high-temperature, and low-activation research conditions.

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