共找到 93 条与 核燃料元件及其分析试验方法 相关的标准,共 7 页
Solvent Extraction-Liquid Scintillation Counting Method for Determination of 99Tc in Reprocessed Uranium Trioxide Powder
Determination of Particle Size of Reprocessed Uranium Trioxide Powder by Laser Diffraction Method
Applied performance test of boron-containing aluminum-based neutron absorbing materials Part 1: Uniform corrosion test method
Applied performance test of boron-containing aluminum-based neutron absorbing materials-Part 5: Short-term high-temperature test method
Zirconium alloy pipes for fuel cladding in pressurized water reactor nuclear power plants
The document is valid for components, i.e. machines, apparatus, devices, remote handling devices and tools, which are used or remote handled in hot cells with lead or concrete shieldings. The document can also be applied to components in other areas of nuclear installations with the necessity for remote handling, such as reactors, fusion reactor power plants and high energy particle accelerators.
Components for hot cells - Requirements on design for remote handling
Determination of Moisture Content in Reprocessed UO3 Powder by Karl Fischer Coulometric Method
Automatic potentiometric titration method for determination of uranium content in reprocessed uranium trioxide powder
Determination of nitrogen content in reprocessed uranium trioxide powder by distillation-Nessler reagent spectrophotometry
Guidelines for Sampling Plutonium Dioxide at Nuclear Fuel Reprocessing Plants
Determination of carbon and sulfur in reprocessed uranium trioxide powder by high-frequency combustion infrared absorption method
Determination of twenty-eight impurity elements such as silver in post-processed uranium trioxide powder by inductively coupled plasma atomic emission spectrometry
Determination of Fluorine, Chlorine and Bromine in Reprocessed Uranium Trioxide Powder by Pyrohydrolysis-Ion Chromatography
Mixed KED/XRF method for determination of uranium and plutonium in spent fuel reprocessing solution
Dissolution method of plutonium material analysis sample
Determination of tantalum, thorium and hafnium in uranium dioxide powders and pellets by inductively coupled plasma atomic emission spectrometry
Test method for thermal stability of sintered uranium dioxide pellets
Determination of Uranium Isotopic Abundance in Uranium Dioxide Powder and Pellets by Thermal Ionization Mass Spectrometry
Determination of Equivalent Water Content in Fuel Rods by Gas Chromatography
γ-ray transmission method for detection of pellet gap and cavity length in pressurized water reactor fuel rods
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