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Instant release of fission products in leaching experiments with high burn-up nuclear fuels in the framework of the Euratom project FIRST- Nuclides

Journal of nuclear materials, 2017-02, Vol.484, p.307-323

2017

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Review of experimental database to support nuclear power plant safety analyses in SGTR and LOCA domains

Annals of nuclear energy, 2023-12, Vol.193, p.110001, Article 110001

2023

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Development of new cladding types for nuclear fuel

IOP conference series. Materials Science and Engineering, 2020-08, Vol.903 (1), p.12004

2020

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Nanophotonics of biomaterials and inorganic nanostructures

Journal of physics. Conference series, 2017-01, Vol.794 (1), p.12004

2017

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Hydrogen uptake of zirconium alloys in defective fuel rods: Experiment and numerical model

Annals of nuclear energy, 2024-09, Vol.204, p.110539, Article 110539

2024

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Neutron Irradiation of Zirconium Alloys in the Budapest Research Reactor

IOP conference series. Materials Science and Engineering, 2020-08, Vol.903 (1), p.12052

2020

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High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys

Progress in nuclear energy (New series), 2010, Vol.52 (1), p.19-36

2010

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Cladding oxidation during air ingress. Part I: Experiments on air ingress

Annals of nuclear energy, 2016-07, Vol.93, p.4-17

2016

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Impact of thermal and chemical treatment on the mechanical properties of E110 and E110G cladding tubes

Nuclear Engineering and Technology, 2019, 51(2), , pp.518-525

2019

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Optical properties of Zr and ZrO2

Applied surface science, 2017-11, Vol.421, p.744-747

2017

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Experimental simulation of the Paks-2 cleaning tank incident through separate effect and integral tests

Nuclear engineering and design, 2011-03, Vol.241 (3), p.573-581

2011

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Extending the application range of a fuel performance code from normal operating to design basis accident conditions

Journal of nuclear materials, 2008-12, Vol.383 (1), p.137-143

2008

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Influence of fission products on ruthenium oxidation and transport in air ingress nuclear accidents

Journal of nuclear materials, 2010-01, Vol.396 (2-3), p.208-217

2010

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Effects of different surfaces on the transport and deposition of ruthenium oxides in high temperature air

Journal of nuclear materials, 2012, Vol.420 (1), p.297-306

2012

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Numerical analyses of an ex-core fuel incident: Results of the OECD-IAEA Paks Fuel Project

Nuclear engineering and design, 2010-03, Vol.240 (3), p.538-549

2010

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Kinetic studies of the α– β phase transition in the Zr1%Nb cladding for nuclear reactors

Journal of nuclear materials, 2011-07, Vol.414 (2), p.88-91

2011

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Activity release from the damaged spent VVER-fuel during long-term wet storage

Radiochimica acta, 2010-01, Vol.98 (4)

2010

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Investigation of aerosols released at high temperature from nuclear reactor core models

Journal of nuclear materials, 2000-12, Vol.282 (2), p.205-215

2000

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Severe accident research in the core degradation area: An example of effective international cooperation between the European Union (EU) and the Commonwealth of Independent States (CIS) by the International Science and Technology Center

Nuclear engineering and design, 2012-11, Vol.252, p.226-241

2012

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European expert network for the reduction of uncertainties in severe accident safety issues (EURSAFE)

Nuclear engineering and design, 2005-02, Vol.235 (2), p.309-346

2005

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WITHDRAWN: Extending the application range of a fuel performance code from normal operating to design basis accident conditions

Journal of nuclear materials, 2007-10

2007

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Impact of thermal and chemical treatment on the mechanical properties of E110 and E110G cladding tubes

Nuclear engineering and technology, 2019, Vol.51 (2), p.518-525

2019

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Analyses of design extension conditions without significant fuel degradation for operating nuclear power plants: An OECD/NEA review

Nuclear engineering and design, 2024-08, Vol.425, p.113320, Article 113320

2024

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SARNET2 benchmark on air ingress experiments QUENCH-10, -16

Annals of nuclear energy, 2014-12, Vol.74 (C), p.12-23

2014

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Core loss during a severe accident (COLOSS)

Nuclear engineering and design, 2005-02, Vol.235 (2), p.173-198

2005

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Instant release of fission products in leaching experiments with high burn-up nuclear fuels in the framework of the Euratom project FIRST- Nuclides

Review of experimental database to support nuclear power plant safety analyses in SGTR and LOCA domains

Development of new cladding types for nuclear fuel

Nanophotonics of biomaterials and inorganic nanostructures

Hydrogen uptake of zirconium alloys in defective fuel rods: Experiment and numerical model

Neutron Irradiation of Zirconium Alloys in the Budapest Research Reactor

High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys

Cladding oxidation during air ingress. Part I: Experiments on air ingress

Impact of thermal and chemical treatment on the mechanical properties of E110 and E110G cladding tubes

Optical properties of Zr and ZrO2

Experimental simulation of the Paks-2 cleaning tank incident through separate effect and integral tests

Extending the application range of a fuel performance code from normal operating to design basis accident conditions

Influence of fission products on ruthenium oxidation and transport in air ingress nuclear accidents

Effects of different surfaces on the transport and deposition of ruthenium oxides in high temperature air

Numerical analyses of an ex-core fuel incident: Results of the OECD-IAEA Paks Fuel Project

Kinetic studies of the α– β phase transition in the Zr1%Nb cladding for nuclear reactors

Activity release from the damaged spent VVER-fuel during long-term wet storage

Investigation of aerosols released at high temperature from nuclear reactor core models

Severe accident research in the core degradation area: An example of effective international cooperation between the European Union (EU) and the Commonwealth of Independent States (CIS) by the International Science and Technology Center

European expert network for the reduction of uncertainties in severe accident safety issues (EURSAFE)

WITHDRAWN: Extending the application range of a fuel performance code from normal operating to design basis accident conditions

Impact of thermal and chemical treatment on the mechanical properties of E110 and E110G cladding tubes

Analyses of design extension conditions without significant fuel degradation for operating nuclear power plants: An OECD/NEA review

SARNET2 benchmark on air ingress experiments QUENCH-10, -16

Core loss during a severe accident (COLOSS)

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