UB Paderborn / Katalog / Suche / in CDI

Sortiert nach

Einfacher Volltextzugriff von (fast) überall

Installieren Sie die LibKey Nomad-Browsererweiterung und erhalten Sie von vielen Webseiten einfachen Zugriff auf lizenzierte Volltexte oder Open Access Publikationen. Mehr erfahren...

DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation

Nuclear engineering and design, 2015-10, Vol.292, p.213-221

2015

Volltextzugriff (PDF)

Model of nuclear fuel pellets densification under irradiation and isothermal conditions: Application to UO2 fuels

Journal of nuclear materials, 2018-11, Vol.510, p.585-595

2018

Volltextzugriff (PDF)

Model of nuclear fuel pellets densification under irradiation and isothermal conditions: Application to UO^sub 2^ fuels

Journal of nuclear materials, 2018-11, Vol.510, p.585

2018

Volltextzugriff (PDF)

Implementation of a microstructural densification model in the DIONISIO nuclear fuel simulation code

Annals of nuclear energy, 2021-03, Vol.152, p.108021, Article 108021

2021

Volltextzugriff (PDF)

An empirical formulation to describe the evolution of the high burnup structure

Journal of nuclear materials, 2015-01, Vol.456, p.174-181

2015

Volltextzugriff (PDF)

Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO

Nuclear engineering and design, 2017-04, Vol.315, p.1-10

2017

Volltextzugriff (PDF)

Simulation with DIONISIO 1.0 of thermal and mechanical pellet-cladding interaction in nuclear fuel rods

Journal of nuclear materials, 2008-02, Vol.374 (1), p.32-43

2008

Volltextzugriff (PDF)

A new irradiation growth model for Zr-based components of nuclear reactors for the DIONISIO code

Nuclear engineering and design, 2021-03, Vol.373, p.111009, Article 111009

2021

Volltextzugriff (PDF)

Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code

Journal of nuclear engineering and radiation science, 2019-04, Vol.5 (2)

2019

Volltextzugriff (PDF)

Model of fracture for the Zry cladding of nuclear fuel rods included in the code DIONISIO 1.0

Nuclear engineering and design, 2008-12, Vol.238 (12), p.3292-3298

2008

Volltextzugriff (PDF)

Simulation of the behaviour of nuclear fuel under high burnup conditions

Annals of nuclear energy, 2014-08, Vol.70, p.147-156

2014

Volltextzugriff (PDF)

Simulation of pellet-cladding thermomechanical interaction and fission gas release

Nuclear engineering and design, 2003-08, Vol.223 (2), p.211-229

2003

Volltextzugriff (PDF)

Two methods of random seed generation to avoid over-segmentation with stochastic watershed: application to nuclear fuel micrographs

Journal of microscopy (Oxford), 2009-10, Vol.236 (1), p.79-86

2009

Volltextzugriff (PDF)

Simulation of isothermal fission gas release

Journal of nuclear materials, 1996-04, Vol.229 (1-3), p.149-154

1996

Volltextzugriff (PDF)

Sexual functioning of women with HIV: a comparison with non-HIV women

The Canadian journal of human sexuality, 2003-06, Vol.12 (2), p.97-108

2003

Volltextzugriff (PDF)

Simulation of isothermal fission gas release

Nuclear engineering and design, 1999-03, Vol.187 (3), p.327-337

1999

Volltextzugriff (PDF)

Simulation of isothermal fission gas release: An analytical solution

Nuclear engineering and design, 1999-03, Vol.187 (3), p.327-337

1999

Volltextzugriff (PDF)

A model to describe the interaction between UO2 and zircaloy in the temperature range 1000–1700°C

Journal of nuclear materials, 1983-05, Vol.116 (1), p.44-54

1983

Volltextzugriff (PDF)

Model to simulate oxidation kinetics of zircaloy-4 during temperature transients between 600 and 800°C

Journal of nuclear materials, 1983-02, Vol.114 (1), p.75-84

1983

Volltextzugriff (PDF)

A model to describe the interaction between UO 2 and zircaloy in the temperature range 1000–1700°C

Journal of nuclear materials, 1983, Vol.116 (1), p.44-54

1983

Volltextzugriff (PDF)

Simulation with the HITO code of the interaction of Zircaloy with uranium dioxide and steam at high temperatures

Journal of nuclear materials, 1991-11, Vol.185 (1), p.96-113

1991

Volltextzugriff (PDF)

Diffusion in a semi-infinite system with a moving interphase considering solvent density change: application to the oxidation of zirconium

Journal of nuclear materials, 1981-01, Vol.96 (1-2), p.127-140

1981

Volltextzugriff (PDF)

Model to simulate parabolic followed by linear oxidation kinetics

Oxidation of metals, 1988-02, Vol.29 (1-2), p.153-167

1988

Volltextzugriff (PDF)

Model to simulate high temperature oxidation kinetics of zircaloy-4: Parabolic and linear behaviour

Journal of nuclear materials, 1982-01, Vol.110 (1), p.11-19

1982

Volltextzugriff (PDF)

Divergent genomic trajectories predate the origin of animals and fungi

Nature (London), 2022-09, Vol.609 (7928), p.747-753

2022

Volltextzugriff (PDF)

1 – 25 von 189

Suche als RSS-Feed

Suchergebnisse filtern

Filter anzeigen

Nur zeigen

Geprüft (Peer-Review)
(164)
Mit Volltextzugriff
(154)

Publikationsform

Artikel
(170)
Buchkapitel
(10)
Bücher
(6)
Reviews
(2)
Texte
(1)

Sprache

1 weiteren anzeigen...

Weniger anzeigen...

Erscheinungsjahr

n.n

Thema

15 weitere anzeigen...

Weniger anzeigen...

Zeitschrift / Serie

5 weitere anzeigen...

Weniger anzeigen...

Neu hinzugefügt

... seit 30 Tagen
(1)
... seit 90 Tagen
(4)

Menü

Weitere Dienste

Einstellungen

DIONISIO 2.0: New version of the code for simulating a whole nuclear fuel rod under extended irradiation

Model of nuclear fuel pellets densification under irradiation and isothermal conditions: Application to UO2 fuels

Model of nuclear fuel pellets densification under irradiation and isothermal conditions: Application to UO^sub 2^ fuels

Implementation of a microstructural densification model in the DIONISIO nuclear fuel simulation code

An empirical formulation to describe the evolution of the high burnup structure

Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO

Simulation with DIONISIO 1.0 of thermal and mechanical pellet-cladding interaction in nuclear fuel rods

A new irradiation growth model for Zr-based components of nuclear reactors for the DIONISIO code

Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code

Model of fracture for the Zry cladding of nuclear fuel rods included in the code DIONISIO 1.0

Simulation of the behaviour of nuclear fuel under high burnup conditions

Simulation of pellet-cladding thermomechanical interaction and fission gas release

Two methods of random seed generation to avoid over-segmentation with stochastic watershed: application to nuclear fuel micrographs

Simulation of isothermal fission gas release

Sexual functioning of women with HIV: a comparison with non-HIV women

Simulation of isothermal fission gas release

Simulation of isothermal fission gas release: An analytical solution

A model to describe the interaction between UO2 and zircaloy in the temperature range 1000–1700°C

Model to simulate oxidation kinetics of zircaloy-4 during temperature transients between 600 and 800°C

A model to describe the interaction between UO 2 and zircaloy in the temperature range 1000–1700°C

Simulation with the HITO code of the interaction of Zircaloy with uranium dioxide and steam at high temperatures

Diffusion in a semi-infinite system with a moving interphase considering solvent density change: application to the oxidation of zirconium

Model to simulate parabolic followed by linear oxidation kinetics

Model to simulate high temperature oxidation kinetics of zircaloy-4: Parabolic and linear behaviour

Divergent genomic trajectories predate the origin of animals and fungi

Suchergebnisse filtern