21
Aspekte des Einsatzes von Systemen zur Transmutation radioaktiver Stoffe : Neutronik, Technik, Sicherheitsverhalten [E-Book] /
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Jahrestagung Kerntechnik. 1996 : Tagungsbericht : Mannheim, 21.05.96-23.05.96 /
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23
Berechnung des Spaltprodukttransportes in SiC-beschichteten Brennelementen für Hochtemperaturreaktoren [E-Book] /
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24
Physics of plutonium recycling vol 0003: void reactivity effect in pressurized water reactors.
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1995
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Physics of plutonium recycling vol 0002: plutonium recycling in pressurized water reactors.
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1995
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26
Managing the plutonium surplus: applications and technical options : NATO advanced research workshop on managing the plutonium surplus: applications and technical options: proceedings : London, 24.01.94-25.01.94 /
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27
Guidebook on non-destructive examination of water reactor fuel.
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1991
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28
Zerstörungsfreie Bestimmung der Uran-235-Anreicherung in Gasultrazentrifugen- Anreicherungsanlagen [E-Book] /
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Irradiation behaviour of advanced fuel elements for the helium-cooled high temperature reactor (HTR) : presented at the 7th CIMTEC World Ceramic Congress at Montecatini Therme, Italy, 24-30 June 1990 [E-Book] /
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Brennstäbe von Leichtwasserreaktoren.
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31
Kritikalitaetsdaten zu wichtigen bei der Brennelementherstellung auftretenden U(5)- Verbindungen und zu MOX(15)- Spaltstoffsystemen im trockenen und moderierten Zustand.
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Krug, H.
1990
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Plutonium fuel : an assessment : report /
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1989
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33
Metallographie und Thermoanalyse von keramischen Kernbrennstoffen: ein Handbuch für Laboranten und Versuchsingenieure.
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34
Daten und Informationen zu ausländischen Anlagen im Bereich der Kernbrennstoffversorgung.
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Mester, W.
1988
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35
Safety analysis report of Uranium Dioxide Fuel Laboratory Nuclear Research Centre Inchas, Egypt [E-Book] /
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Fuel elements and assemblies : International conference on structural mechanics in reactor technology. 0009: transactions. vol C : SMIRT. 0009: transactions : Lausanne, 17.08.87-21.08.87.
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37
Das Bersten von Brennstabhüllrohren aus Zirkaloy unter Innendruckbelastung : eine Auswertung experimentell begründeter Rechenmodelle.
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Die internationale Bewertung des nuklearen Brennstoffkreislaufs : ein Versuch zur Konsensfindung in der internationalen Nuklearpolitik [E-Book] /
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Long-term testing of HTR fuel elements in the Federal Republic of Germany [E-Book] /
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Fission product behavior in ceramic oxide fuel : Symposium on fission product behavior in ceramic oxide fuel: proceedings : Annual meeting of the American Ceramic Society. 0087 : Cincinnati, OH, 06.05.85-07.05.85.
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