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DIN 25710:1995-10

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DIN 25710:1995-10

Determination of the hydrogen content and the equivalent humidity in uranium dioxide powders and pellets of UO2, (U,Gd)O2 and (U,Pu)O2 with the carrier gas method

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Nuclear fuel contains adsorbed water, crystal water and other hydrogen containing impurities. They are released and destroyed by heating above 1800 °C in argon or nitrogen. The resulting gas is purified with oxidation and adsorption colums, the hydrogen separated with a molecular sieve, and determined in a heat conductivity measurement cell.

Author DIN
Editor DIN
Document type Standard
Format File
expiration_de_validite 2010-05-31
ICS 27.120.30 : Fissile materials and nuclear fuel technology
Number of pages 2
Replace DIN 25710 (1994-06)
Year 1990
Document history DIN 25710 (1995-10)
Country Germany
Keyword 25710