DIN 25709:1995-10
Withdrawn Standard
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DIN 25709:1995-10

Post-sintering test for UO<(Index)2> and UO<(Index)2>/Gd<(Index)2>O<(Index)3> nuclear fuel pellets

Summary

The in-pile density increase of ceramic nuclear fuel tablets after a burn-up of ca. 10 GWd/HU depends on various parameters such as pore size and structure, grain size etc. It is determined by a pre-heating density measurement, followed by another such measurement after the heat treatment under defined conditions. From the difference of both measurements, the post-sintering effect is determined.

Technical characteristics

Publisher Deutsche Institut für Normung e.V. (DIN)
Publication Date 10/01/1995
Page Count 2
EAN ---
ISBN ---
Weight (in grams) ---
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