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Katalin Kulacsy

Observed names: K. Kulacsy, KULACSY Katalin
ORCID: 0000-0003-3224-8943
Observed ORCID: 0000-0003-3224-8943
OpenAlex ID: A5074489939
Unit mechanisms of fission gas release: Current understanding and future needs
2018 · Michael Tonks, David Andersson, et al. · Journal of Nuclear Materials · 145
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Thermodynamic length, time, speed, and optimum path to minimize entropy production
1996 · L. Diósi, K. Kulacsy, et al. · The Journal of Chemical Physics · 62
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Mechanistic model for the fragmentation of the high-burnup structure during LOCA
2015 · Katalin Kulacsy · Journal of Nuclear Materials · 31
High-temperature steam oxidation kinetics of the E110G cladding alloy
2016 · Márton Király, Katalin Kulacsy, et al. · Journal of Nuclear Materials · 23
Post-test examinations on Zr-1%Nb claddings after ballooning and burst, high-temperature oxidation and secondary hydriding
2018 · Eszter Kozsda-Barsy, Katalin Kulacsy, et al. · Journal of Nuclear Materials · 17
State of the art of fuel micro-mechanical modelling: From atomic scale to engineering laws in fuel performance codes
2022 · Bruno Michel, Michael Welland, et al. · Journal of Nuclear Materials · 11
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Fuel Performance of Light Water Reactors (Uranium Oxide and MOX)
2019 · Daniel Baron, Lars Hallstadius, et al. · Elsevier eBooks · 11
A method for prompt calculation of neutron flux from measured SPND currents
1997 · Katalin Kulacsy, Iván Lux · Annals of Nuclear Energy · 11
High-Temperature Secondary Hydriding Experiments with E110 and E110G Claddings
2018 · Zoltán Hózer, Imre Nagy, et al. · 9
The fuel behaviour code FUROM and its high burn-up simulation capabilities
2018 · János Gadó, Ágnes Griger, et al. · Nuclear Engineering and Design · 6
Numerical simulation of the telescope sipping of a leaking VVER fuel assembly
2016 · Péter Szabó, Zoltán Hózer, et al. · Annals of Nuclear Energy · 6
New burst criteria for loss of coolant accidents radiological consequences assessment
2024 · Tatiana Taurines, Tony Glantz, et al. · Annals of Nuclear Energy · 5
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International Fuel Performance Study of Fresh Fuel Experiments for Pcmi Effects During Ria Experiments
2024 · Seokbin Seo, Charles Folsom, et al. · Nuclear Engineering and Design · 4
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The non-uniform high-temperature oxidation of Zr–1%Nb cladding – A numerical model
2021 · Eszter Barsy, Péter Szabó, et al. · Progress in Nuclear Energy · 3
International study of fuel performance codes for failure predictions of pre-hydrided Zircaloy cladding during RIAs
2026 · Seokbin Seo, Charles Folsom, et al. · Nuclear Engineering and Design
Lessons Learned from Safety Analyses Including a Design Criterion for Cladding Hoop Stress
2021 · Katalin Kulacsy
MTA EK Activities in the IAEA FUMAC CRP
2019 · Katalin Kulacsy
Further comments on the sequential probability ratio testing methods
1997 · Katalin Kulacsy · Annals of Nuclear Energy
Elements of linear transport theory
1995 · Katalin Kulacsy
Works count: 20
Citation count: 344
H-index: 9
I10-index: 8
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