1
Secondary uranium phases of spent nuclear fuel - coffinite, USiO4, and studtite, UO4 . 4H2O - synthesis, characterization, and investigations regarding phase stability /
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2
Räumlich hoch aufgelöste Modellierung des Spaltproduktverhaltens in einem HTR-Core mit kugelförmigen oder prismatischen Brennelementen /
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3
High-quality thorium TRISO fuel performance in HTGRs /
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4
Monazite-type ceramics for conditioning of minor actinides : structural characterization and properties /
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5
Untersuchungen zum Sicherheits- und Transmutationsverhalten innovativer Brennstoffe für Leichtwasserreaktoren /
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6
Material properties/oxide fuels for light water reactors and fast neutron reactors /
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7
Advanced fuels/fuel cladding/nuclear fuel performance modeling and simulation /
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8
Material performance and corrosion/waste materials /
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9
Thermophysical properties of materials for nuclear engineering : a tutorial and collection of data /
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2008
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10
Nuclear safeguards, security and nonproliferation : achieving security with technology and policy /
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11
A comparision of the WWER-1000 reactor neutron power change processes for the different variants of the (Th, U, Pu)O2 fuel loading /
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12
The nuclear fuel of pressurized water reactors and fast reactors : design and behaviour /
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13
Jahrestagung Kerntechnik. 1998 : Tagungsbericht : 26.-28. Mai 1998, München Park Hilton, München /
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14
Jahrestagung Kerntechnik. 1996 : Tagungsbericht : Mannheim, 21.05.96-23.05.96 /
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15
Physics of plutonium recycling vol 0003: void reactivity effect in pressurized water reactors.
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1995
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16
Physics of plutonium recycling vol 0002: plutonium recycling in pressurized water reactors.
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1995
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17
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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18
Guidebook on non-destructive examination of water reactor fuel.
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1991
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19
Brennstäbe von Leichtwasserreaktoren.
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20
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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