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TNJB - Nuclear reactor materials
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FNX - Carbon, carbon materials
Theses
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TNJB - Nuclear reactor materials
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FNX - Carbon, carbon materials
Theses
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1
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Oxydationsverhalten von Coat-Mix-Materialien in Luft bei Temperaturen um 800 K [E-Book] /
Hillen, M.
1983
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2
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Stereometrische Analyse von grafitischen Reaktorwerkstoffen [E-Book] /
Uhlenbruck, H.
1978
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Ein Verfahren zur Bestimmung der Wärmeleitfähigkeit von neutronenbestrahlten Graphiten bei Temperaturen zwischen 50 und 1000C [E-Book] /
Binkele, Ludolf
1974
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Electronic Edition
Material Type
Book
3
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ZB
3
Name
Nickel, Hubertus
2
Binkele, Ludolf
1
Delle, Wolfgang W.
1
Hillen, M.
1
Koizlik, Karl
1
Luhleich, H.
1
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Uhlenbruck, H.
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Subject
graphite
1
pyrolytic graphite
1
Classification
FNX - Carbon, carbon materials
TNJB - Nuclear reactor materials
FHEM - Image analysis in microscopy, stereology
1
FPTN - Corrosion of specific materials
1
Language
German
3
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