Book/Report FZJ-2018-01584

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Tritiumgewinnung aus Zircaloyhüllrohren abgebrannter LWR-Brennelemente

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1981
Kernforschungsanlage Jülich, Verlag Jülich

Jülich : Kernforschungsanlage Jülich, Verlag, Berichte der Kernforschungsanlage Jülich 1715, 36 p. ()

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Report No.: Juel-1715

Abstract: Tritium can be desorbed up to 98 % by a simple method from LWR spent fuel cladding hulls. To accomplish this, cladding hulls are induction heated at temperatures up to 1100°C. The desorption is possible using hydrogen or with vacuum. Zircaloy - IV cladding samples which received a burn up of 30.000 MWd/t at a power density of 180 W / cm yielded 1140 $\mu$Ci tritium per gramme of zircaloy. The results of the desorption experiments are confirmed by a dissolution method and control tests with standardized tritium samples.


Contributing Institute(s):
  1. Publikationen vor 2000 (PRE-2000)
Research Program(s):
  1. 899 - ohne Topic (POF3-899) (POF3-899)

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OpenAccess
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Open Access

 Datensatz erzeugt am 2018-03-02, letzte Änderung am 2021-01-29


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