共找到 6 条与 相关的标准,共 1 页
Packaging of uranium hexafluoride (UF6) for transport
Ceramography of sintered nuclear fuel tablets
Specifies an analytical method which can be used within the concentration range of 1 鎔 to 0,001 g of fluorine per gram of the sample. Specifies the principle, the reagents, the apparatus, the sampling, the procedure, the expression of results and the test report.
Uranium metal, uranium dioxide powder and pellets, and uranyl nitrate solutions; determination of fluorine content; fluoride ion selective electrode method
The standard describes a method for the determination of the uranium content in UO(NO) solutions. After transfer into a nitric acid solution, uranium can also be determined in UF, UOF and powders or tablets of UO, UO, UO/GdO, (U,Pu)O,(Th,U)O, and UAL. The potentiometric titration is only little influenced by other ions.#,,#
Determination of the uranium content of nuclear fuels; potentiometric method based on the modified Davies and Gray method
This standard specifies a method for the determination of the apparent density and vibrated density of free-flowing nuclear fuel powder used for pelletizing and sintering of nuclear fuel pellets. The powder can consist of grains, granules, spheres or other types of particle. The method can be applied to fuel powders such as UO, PuO, ThO and powder mixtures such as UO-PuO and UO-GdO.
Determination of apparent density and vibrated density of nuclear fuel powder
Nuclear energy; Fissile materials; Principles of criticality safety in handling and processing
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