1
Optimale Auslegung von Brennstoffkreisläufen des THTR bei Zwei-Typen-Beladung.
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“...TNDF - Gas cooled reactor fuel elements...”
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Thorium uranium fuel cycles in large H.T.G.R. : paper to be presented at the Symposium on the Assessment Studies for a H.T.G.R., Bournemouth, 7th and 8th April, 1964.
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“...TNDF - Gas cooled reactor fuel elements...”
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Studie zur Schliessung der HTR-Brennstoffkreislaufes /
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“...TNDF - Gas cooled reactor fuel elements...”
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