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Fission product release and microstructure changes during laboratory annealing of a very high burn-up fuel specimen

Journal of nuclear materials, 2008-07, Vol.377 (2), p.313-324

2008

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SIMS analysis of an UO2 fuel irradiated at low temperature to 65 MWd/kgHM

Journal of nuclear materials, 2009-09, Vol.393 (2), p.212-223

2009

Volltextzugriff (PDF)

Matrix swelling rate and cavity volume balance of UO2 fuels at high burn-up

Journal of nuclear materials, 2005-11, Vol.346 (2-3), p.131-144

2005

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On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100 MWd/kgHM

Journal of nuclear materials, 2006-03, Vol.350 (1), p.19-39

2006

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On the oxidation state of UO2 nuclear fuel at a burn-up of around 100 MWd/kgHM

Journal of nuclear materials, 2005-10, Vol.345 (2-3), p.192-205

2005

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Ein induktives Modell fuer die Ausbreitung der Normalleitung im supraleitenden Magneten

Goll, W

2016

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On the condition of UO2 nuclear fuel irradiated in a PWR to a burn-up in excess of 110 MWd/kgHM

Journal of nuclear materials, 2016-12, Vol.481, p.88-100

2016

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Short-time creep and rupture tests on high burnup fuel rod cladding

Journal of nuclear materials, 2001-03, Vol.289 (3), p.247-253

2001

Volltextzugriff (PDF)

SIMS analysis of an UO2 fuel irradiated at low temperature to 65MWd/kgHM

Journal of nuclear materials, 2009-09, Vol.393 (2), p.212-223

2009

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Effect of inhomogeneity on the level of fission gas and caesium release from OCOM MOX fuel during irradiation

Journal of nuclear materials, 1996-02, Vol.228 (1), p.8-17

1996

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Further observations on OCOM MOX fuel: microstructure in the vicinity of the pellet rim and fuel — cladding interaction

Journal of nuclear materials, 1997-06, Vol.245 (2), p.169-178

1997

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SIMS analysis of an UO 2 fuel irradiated at low temperature to 65 MWd/kgHM

Journal of nuclear materials, 2009, Vol.393 (2), p.212-223

2009

Volltextzugriff (PDF)

SIMS analysis of an UO(2) fuel irradiated at low temperature to 65 MWd/kgHM

Journal of nuclear materials, 2009-09, Vol.393 (2), p.212-223

2009

Volltextzugriff (PDF)

SIMS analysis of an UO sub(2) fuel irradiated at low temperature to 65 MWd/kgHM

Journal of nuclear materials, 2009-09, Vol.393 (2), p.212-223

2009

Volltextzugriff (PDF)

Matrix swelling rate and cavity volume balance of UO 2 fuels at high burn-up

Journal of nuclear materials, 2005, Vol.346 (2), p.131-144

2005

Volltextzugriff (PDF)

On the Thermal Conductivity of UO sub(2) Nuclear Fuel at a High Burn-Up of Around 100 MWd/kgHM

Journal of nuclear materials, 2006-03, Vol.350 (1), p.19-19

2006

Volltextzugriff (PDF)

On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100MWd/kgHM

Journal of nuclear materials, 2006-03, Vol.350 (1), p.19-39

2006

Volltextzugriff (PDF)

On the thermal conductivity of UO 2 nuclear fuel at a high burn-up of around 100 MWd/kgHM

Journal of nuclear materials, 2006, Vol.350 (1), p.19-39

2006

Volltextzugriff (PDF)

On the oxidation state of UO2 nuclear fuel at a burn-up of around 100MWd/kgHM

Journal of nuclear materials, 2005-10, Vol.345 (2-3), p.192-205

2005

Volltextzugriff (PDF)

Transition Metal Coordination Compounds of Bisamidobispyridyl Ligands

European journal of inorganic chemistry, 1998-12, Vol.1998 (12), p.2041-2049

1998

Volltextzugriff (PDF)

Irradiation behaviour of MOX fuel: Results of an EPMA investigation

Nuclear engineering and design, 1991-10, Vol.131 (1), p.1-16

1991

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Potentiometric and spectroscopic studies of transition metal complexes of bis(imidazolyl) and bis(pyridyl) derivatives of amino acids

Inorganica Chimica Acta, 1998-12, Vol.283 (1), p.233-242

1998

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Swimming pool requirements in schools and what the health officer should know about them

Der Offentliche Gesundheitsdienst, 1957-02, Vol.18 (11), p.477

GOLL, W

1957

Volltextzugriff (PDF)

Über die synthese von π-sandwich-komplexen des vanadins mittels der isopropyl-grignard-methode

Journal of organometallic chemistry, 1974-05, Vol.71 (2), p.257-262

1974

Volltextzugriff (PDF)

Irradiation Behavior of UO sub 2 /PuO sub 2 Fuel in Light Water Reactors

Nuclear technology, 1993-04, Vol.102 (1), p.29-46

1993

Volltextzugriff (PDF)

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Fission product release and microstructure changes during laboratory annealing of a very high burn-up fuel specimen

SIMS analysis of an UO2 fuel irradiated at low temperature to 65 MWd/kgHM

Matrix swelling rate and cavity volume balance of UO2 fuels at high burn-up

On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100 MWd/kgHM

On the oxidation state of UO2 nuclear fuel at a burn-up of around 100 MWd/kgHM

Ein induktives Modell fuer die Ausbreitung der Normalleitung im supraleitenden Magneten

On the condition of UO2 nuclear fuel irradiated in a PWR to a burn-up in excess of 110 MWd/kgHM

Short-time creep and rupture tests on high burnup fuel rod cladding

SIMS analysis of an UO2 fuel irradiated at low temperature to 65MWd/kgHM

Effect of inhomogeneity on the level of fission gas and caesium release from OCOM MOX fuel during irradiation

Further observations on OCOM MOX fuel: microstructure in the vicinity of the pellet rim and fuel — cladding interaction

SIMS analysis of an UO 2 fuel irradiated at low temperature to 65 MWd/kgHM

SIMS analysis of an UO(2) fuel irradiated at low temperature to 65 MWd/kgHM

SIMS analysis of an UO sub(2) fuel irradiated at low temperature to 65 MWd/kgHM

Matrix swelling rate and cavity volume balance of UO 2 fuels at high burn-up

On the Thermal Conductivity of UO sub(2) Nuclear Fuel at a High Burn-Up of Around 100 MWd/kgHM

On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100MWd/kgHM

On the thermal conductivity of UO 2 nuclear fuel at a high burn-up of around 100 MWd/kgHM

On the oxidation state of UO2 nuclear fuel at a burn-up of around 100MWd/kgHM

Transition Metal Coordination Compounds of Bisamidobispyridyl Ligands

Irradiation behaviour of MOX fuel: Results of an EPMA investigation

Potentiometric and spectroscopic studies of transition metal complexes of bis(imidazolyl) and bis(pyridyl) derivatives of amino acids

Swimming pool requirements in schools and what the health officer should know about them

Über die synthese von π-sandwich-komplexen des vanadins mittels der isopropyl-grignard-methode

Irradiation Behavior of UO sub 2 /PuO sub 2 Fuel in Light Water Reactors

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