Authors List
| Abushamah Hussein |
| No. 108 |
|
A study of integration of Liquid Air Energy Storage (LAES) technology to nuclear district heating facility TEPLATOR |
| No. 115 |
|
Integration of Heat-only Small Modular Reactor with Thermally Driven Systems |
| Alfinito Federico |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Ambrosini Walter |
| No. 410 |
|
Extrapolating Phenomena Observed with Carbon Dioxide to Supercritical Water Reactor Conditions |
| No. 412 |
|
Sensitivity analyses by a CFD model on water-wall behaviour in a LW SMR during SBO conditions |
| Ambrožič Klemen |
| No. 906 |
|
Fast neutron fluence profiling at the JSI TRIGA reactor irradiation facility |
| Andrighetto Alberto |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Andronopoulos Spyros |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| No. 1002 |
|
Licensing fusion facilities based on the ITER and DEMO paradigms |
| Apostol Minodora |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| Arefin Md Arman |
| No. 419 |
|
Direct Contact Condensation Induced Water Hammer Simulation Using Computational Fluid Dynamics Code |
| Arzenton Alberto |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Asti Mattia |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Auria Francesco |
| No. 407 |
|
Sensitivity studies on Reverse Natural Circulation in the PKL facility by using RELAP5 mod3.2mz |
| Awan Muhammad Zaki Abbas |
| No. 918 |
|
An Analytical Model of Heat Transfer in a Fuel Rod Suitable for Neutron Calculations |
| Bachmann Christian |
| No. 427 |
|
EU DEMO upper port transfer cask CFD analysis |
| Bakr Arby Mahmoud |
| No. 1013 |
|
Radiation Tolerant Neutron Activation Detector for Compact Inertial Electrostatically Confined Fusors |
| Barbero Daniela |
| No. 109 |
|
Nuclear Power Plant Cooling Tower Steam Emission Environmental Impact |
| Batki Bálint |
| No. 914 |
|
Burnup-dependent group constant parametrization by applying different machine learning methodologies |
| Benčik Vesna |
| No. 422 |
|
Analysis of Steam Generator Tube Rupture (SGTR) Accident using RELAP5/MOD 3.3 and TRACE 5.0p5 Codes |
| Bergant Robert |
| No. 116 |
|
Potential Of Using SMR Reactors At Coal-Fired Power Plant Locations |
| Bestion Dominique |
| No. 407 |
|
Sensitivity studies on Reverse Natural Circulation in the PKL facility by using RELAP5 mod3.2mz |
| Bizjak Rok |
| No. 501 |
|
Krško NPP Spent Fuel Dry Storage Project – Technology and Implementation Overview |
| Blascovich Alessandro |
| No. 604 |
|
On the reasons and extent of NEK's seismic instrumentation upgrade |
| Boccelli Riccardo |
| No. 912 |
|
OpenMC Analysis of TRIGA Mark II Reactor Void and Temperature Reactivity Coefficients |
| Bogdanović Leon |
| No. 1009 |
|
Divertor Armor Damage Estimation and Dynamics of Secondary Tungsten Plasma Simulation with TOKES in ITER |
| Bois Guillaume |
| No. 416 |
|
The 3D DNS simulation of a Taylor bubble in counter-current flow with a turbulent wake using the Front-Tracking method in TrioCFD |
| Bortolussi Silva |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Božnar Marija Zlata |
| No. 109 |
|
Nuclear Power Plant Cooling Tower Steam Emission Environmental Impact |
| Breznik Thomas |
| No. 710 |
|
Analysis of analogue data transmission of dose rate measurements over the HAM amateur radio network in the event of an emergency and possible failure of other communication channels |
| Buck Michael |
| No. 402 |
|
Analysis of an innovative passive heat removal system for station blackout scenario |
| Bučar Tinkara |
| No. 205 |
|
Evaluation of the Justification for Using Consumer Products and Geological Samples Containing Radioactive Substances |
| Burian Ondřej |
| No. 108 |
|
A study of integration of Liquid Air Energy Storage (LAES) technology to nuclear district heating facility TEPLATOR |
| Burlot Alan |
| No. 416 |
|
The 3D DNS simulation of a Taylor bubble in counter-current flow with a turbulent wake using the Front-Tracking method in TrioCFD |
| Buzzetti Renato |
| No. 105 |
|
Preliminary feasibility study of coupling between SMR and desalination plant |
| Cai Qingling |
| No. 407 |
|
Sensitivity studies on Reverse Natural Circulation in the PKL facility by using RELAP5 mod3.2mz |
| Calabrese Rolando |
| No. 312 |
|
Thermal creep of MOX fuel: a review of correlations |
| No. 930 |
|
Evaluation of Uncertainties affecting Elastic Properties of MOX fuel |
| Cammi Antonio |
| No. 904 |
|
FEniCSx-OpenMC Coupling for Neutronic Calculation with Temperature Feedback |
| No. 905 |
|
An Innovative Reactivity Control Strategy for Small Modular Reactors |
| No. 912 |
|
OpenMC Analysis of TRIGA Mark II Reactor Void and Temperature Reactivity Coefficients |
| No. 915 |
|
Multi-Physics Model Correction with Data-Driven Reduced Order Modelling |
| No. 916 |
|
OpenMC Model Validation of the TRIGA Mark II Reactor |
| Cancemi Salvatore Angelo |
| No. 105 |
|
Preliminary feasibility study of coupling between SMR and desalination plant |
| Caramello Marco |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| Celarec Daniel |
| No. 604 |
|
On the reasons and extent of NEK's seismic instrumentation upgrade |
| Cestnik Tilen |
| No. 710 |
|
Analysis of analogue data transmission of dose rate measurements over the HAM amateur radio network in the event of an emergency and possible failure of other communication channels |
| Cevikalp Usta Sinem |
| No. 402 |
|
Analysis of an innovative passive heat removal system for station blackout scenario |
| Chapman Neil |
| No. 502 |
|
How will backend issues affect the global deployment of SMRs? |
| Cirillo Roberta |
| No. 804 |
|
Towards Optimized Use of Research Reactors in Europe - Summary and Results |
| Cizelj Leon |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| No. 702 |
|
Development of 3D fracture mechanics submodels for PTS analyses of an RPV with cracks |
| No. 801 |
|
Impact of the ENEN2plus project after one year of implementation |
| No. 1002 |
|
Licensing fusion facilities based on the ITER and DEMO paradigms |
| Coeck Michèle |
| No. 801 |
|
Impact of the ENEN2plus project after one year of implementation |
| Constantin Marin |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| Corradetti Stefano |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Costa Garrido Oriol |
| No. 702 |
|
Development of 3D fracture mechanics submodels for PTS analyses of an RPV with cracks |
| No. 1005 |
|
Development of a Thermo-mechanical Model for DTT PFU |
| Cuellar Fernandez Diego Martin |
| No. 917 |
|
Feasibility study for design and utilization of a cold neutron irradiation facility at the JSI TRIGA reactor |
| Čalič Dušan |
| No. 922 |
|
An overview of research project of the nuclear power plant load follow operation |
| Češarek Janez |
| No. 210 |
|
Transport of Radioactive Material: “The Road to Success – is Always under Construction” |
| Črnič Boštjan |
| No. 710 |
|
Analysis of analogue data transmission of dose rate measurements over the HAM amateur radio network in the event of an emergency and possible failure of other communication channels |
| D'Agostino Giancarlo |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Daifuku Karen |
| No. 801 |
|
Impact of the ENEN2plus project after one year of implementation |
| Dambrosio Antonio |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| De Angelis Alessandro |
| No. 412 |
|
Sensitivity analyses by a CFD model on water-wall behaviour in a LW SMR during SBO conditions |
| de Bilbao Emmanuel |
| No. 707 |
|
Experimental Measurements of Thermophysical Properties of Several Corium Compositions and Influence on Fuel-Coolant Interaction |
| de la Rosa Blul Juan Carlos |
| No. 1002 |
|
Licensing fusion facilities based on the ITER and DEMO paradigms |
| Debelak Klemen |
| No. 109 |
|
Nuclear Power Plant Cooling Tower Steam Emission Environmental Impact |
| Delacroix Jules |
| No. 707 |
|
Experimental Measurements of Thermophysical Properties of Several Corium Compositions and Influence on Fuel-Coolant Interaction |
| Denier Caroline |
| No. 707 |
|
Experimental Measurements of Thermophysical Properties of Several Corium Compositions and Influence on Fuel-Coolant Interaction |
| Di Gennaro Martina |
| No. 409 |
|
Sub-channel analysis of the MYRRHA reactor with OpenFOAM: Numerical assessment of turbulence models |
| Di Luzio Marco |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Di Marco Valerio |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Di Nora Vincenzo Anthony |
| No. 206 |
|
Implementation and application of a GitLab CI-pipeline in support of V&V activities of AC2 |
| Dolšek Matjaž |
| No. 705 |
|
Seismic risk assessment of safety-related SSCs |
| Dominguez Cristina |
| No. 701 |
|
Fuel Cladding Deformation during LOCA: Comparaison between Single-rod and Multi-rod tests |
| Donzella Antonietta |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Draksler Martin |
| No. 427 |
|
EU DEMO upper port transfer cask CFD analysis |
| Dučkić Paulina |
| No. 429 |
|
Usage of Monte Carlo Code Serpent2 for Calculation of FHR Fuel Assembly |
| No. 612 |
|
The Assessment of Dose Rates during MPC Loading and Drying in frame of the Nuclear Power Plant Krško First SFDS Loading Campaign |
| El Shawish Samir |
| No. 302 |
|
Probabilistic assessment of induced intergranular stresses in polycrystalline materials |
| Fackovič Volčanjk Pia |
| No. 117 |
|
Thermal Energy Storage Combined With a Molten Salt Reactor |
| Ferrari Matteo |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Ferretto Danilo |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| Fiorini Gian-Luigi |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| No. 1002 |
|
Licensing fusion facilities based on the ITER and DEMO paradigms |
| Fleming Nina C. |
| No. 928 |
|
Thermal Scattering Law for Zirconium Hydride |
| Flores y Flores Alain |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| Fuzik Kateryna |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| Gajšek Aljoša |
| No. 415 |
|
A mechanistic bubble force model for the development of boiling parameters in high heat flux regimes |
| Galek Vojtech |
| No. 515 |
|
Direct conditioning of liquid organic radioactive waste into a geopolymer matrix |
| No. 517 |
|
Improved Geopolymers For Encapsulation Of Molten Salts From Thermal Treatment Processes |
| Gandini Andrea |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Gerkšič Samo |
| No. 922 |
|
An overview of research project of the nuclear power plant load follow operation |
| GIOT Lydie |
| No. 902 |
|
Uncertainty Propagation of decay data for Decay Heat Calculations: A Monte Carlo Approach |
| Goričanec Tanja |
| No. 910 |
|
Intermediate range detectors for control rod worth measurements with rod insertion method |
| Grasso Giacomo |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| Grašič Boštjan |
| No. 109 |
|
Nuclear Power Plant Cooling Tower Steam Emission Environmental Impact |
| Grgić Davor |
| No. 422 |
|
Analysis of Steam Generator Tube Rupture (SGTR) Accident using RELAP5/MOD 3.3 and TRACE 5.0p5 Codes |
| No. 429 |
|
Usage of Monte Carlo Code Serpent2 for Calculation of FHR Fuel Assembly |
| No. 612 |
|
The Assessment of Dose Rates during MPC Loading and Drying in frame of the Nuclear Power Plant Krško First SFDS Loading Campaign |
| Groudev Pavlin |
| No. 426 |
|
Comparison of the main parameters behavior in VVER 1000 during a MSLB accident for different fuel campaigns |
| Hadrava Jan |
| No. 517 |
|
Improved Geopolymers For Encapsulation Of Molten Salts From Thermal Treatment Processes |
| Haendel Kai-Martin |
| No. 504 |
|
Calculation method for determining neutron-induced nuclide activities in nuclear facilities |
| No. 509 |
|
Uncertainty of Fuel Assembly Burnup in Siemens/KWU PWRs |
| Haghighat Alireza |
| No. 913 |
|
Experimental and Computational Validation of Novel Depletion Algorithm in the RAPID Code System using JSI TRIGA reactor |
| Hamrit Grégoire |
| No. 416 |
|
The 3D DNS simulation of a Taylor bubble in counter-current flow with a turbulent wake using the Front-Tracking method in TrioCFD |
| Hawari Ayman I. |
| No. 928 |
|
Thermal Scattering Law for Zirconium Hydride |
| Hémery Guillaume |
| No. 613 |
|
Early Launch of Validation via an Evolving Engineering Simulator (ELVEES) |
| Herbas Lopez Marco |
| No. 905 |
|
An Innovative Reactivity Control Strategy for Small Modular Reactors |
| Heruc Zoran |
| No. 201 |
|
Use of Commercial grade items in nuclear safety related applications: New developments and guidance |
| Hirooka Shun |
| No. 930 |
|
Evaluation of Uncertainties affecting Elastic Properties of MOX fuel |
| Hofer Markus |
| No. 804 |
|
Towards Optimized Use of Research Reactors in Europe - Summary and Results |
| Hollands Thorsten |
| No. 206 |
|
Implementation and application of a GitLab CI-pipeline in support of V&V activities of AC2 |
| Hruščak Peter |
| No. 613 |
|
Early Launch of Validation via an Evolving Engineering Simulator (ELVEES) |
| Hutson Chris |
| No. 301 |
|
GANEX gamma radiation tolerance methodology |
| Ikonomopoulos Andreas |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| No. 1002 |
|
Licensing fusion facilities based on the ITER and DEMO paradigms |
| Introini Carolina |
| No. 904 |
|
FEniCSx-OpenMC Coupling for Neutronic Calculation with Temperature Feedback |
| No. 905 |
|
An Innovative Reactivity Control Strategy for Small Modular Reactors |
| No. 912 |
|
OpenMC Analysis of TRIGA Mark II Reactor Void and Temperature Reactivity Coefficients |
| No. 915 |
|
Multi-Physics Model Correction with Data-Driven Reduced Order Modelling |
| No. 916 |
|
OpenMC Model Validation of the TRIGA Mark II Reactor |
| Istenič Radko |
| No. 809 |
|
Youngsters about Nuclear Energy – Year 2023 Poll |
| No. 810 |
|
Public Opinion about Nuclear Energy – A Comparison between Youngsters and General Population, Year 2023 Poll |
| Jaćimović Radojko |
| No. 907 |
|
Influence of the temporal variability of neutron fluxes in the carousel of TRIGA Mark IPR-R1 research reactor, CDTN, Brazil, in the k0-method of neutron activation analysis |
| Jazbec Anže |
| No. 923 |
|
Jožef Stefan Institute TRIGA Research Reactor Activities in the Period from September 2022 – August 2023 |
| Jazbinšek Jure |
| No. 106 |
|
Benefits of multi-unit NPP projects during construction phase with full life-cycle cost assessment |
| Ječmenica Radomir |
| No. 429 |
|
Usage of Monte Carlo Code Serpent2 for Calculation of FHR Fuel Assembly |
| Jenčič Igor |
| No. 809 |
|
Youngsters about Nuclear Energy – Year 2023 Poll |
| No. 810 |
|
Public Opinion about Nuclear Energy – A Comparison between Youngsters and General Population, Year 2023 Poll |
| No. 811 |
|
Renovation of the permanent exhibition on nuclear techology |
| Jevnik Aleš |
| No. 606 |
|
RPV threaded hole lubrication device |
| Jiřičková Jana |
| No. 921 |
|
Radiation Damage of SMR Reactor Vessel |
| Kadiroglu Mehmet |
| No. 504 |
|
Calculation method for determining neutron-induced nuclide activities in nuclear facilities |
| Karppinen Ismo |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| No. 1002 |
|
Licensing fusion facilities based on the ITER and DEMO paradigms |
| Kassem Sara |
| No. 410 |
|
Extrapolating Phenomena Observed with Carbon Dioxide to Supercritical Water Reactor Conditions |
| Kavčič Andrej |
| No. 501 |
|
Krško NPP Spent Fuel Dry Storage Project – Technology and Implementation Overview |
| Kecek Adam |
| No. 404 |
|
Application of CFD and system codes to simulation of HERO-2 experiment |
| No. 418 |
|
Simulation of PASI experiment on passive containment heat removal system with MELCOR and ATHLET |
| Kegel Leon |
| No. 502 |
|
How will backend issues affect the global deployment of SMRs? |
| No. 514 |
|
Deep Borehole Disposal as an Alternative Disposal Option for Spent Fuel |
| Kelhar Aleš |
| No. 116 |
|
Potential Of Using SMR Reactors At Coal-Fired Power Plant Locations |
| Kickhofel John |
| No. 201 |
|
Use of Commercial grade items in nuclear safety related applications: New developments and guidance |
| Kinghorn-Mills Jake |
| No. 502 |
|
How will backend issues affect the global deployment of SMRs? |
| Klein-Heßling Walter |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| Kljenak Ivo |
| No. 419 |
|
Direct Contact Condensation Induced Water Hammer Simulation Using Computational Fluid Dynamics Code |
| No. 420 |
|
RELAP5 Validation Against Experiment Performed in SIRIO Experimental Facility |
| Kokalj Janez |
| No. 708 |
|
Modelling approach for premixing phase in combination of melt jet breakup and premixed layer formation of melt spread |
| No. 713 |
|
Uncertainty Analysis of Severe Accident Scenario in Krško NPP |
| Kolykhanov Victor |
| No. 931 |
|
Angular Spectrum of the Diffusion Neutron Flux |
| Končar Boštjan |
| No. 401 |
|
TRACE Analysis of Total Loss of Feedwater in PWR |
| No. 415 |
|
A mechanistic bubble force model for the development of boiling parameters in high heat flux regimes |
| No. 427 |
|
EU DEMO upper port transfer cask CFD analysis |
| No. 1005 |
|
Development of a Thermo-mechanical Model for DTT PFU |
| Končar Mihael Boštjan |
| No. 425 |
|
Measurement of Radiative Transport Properties of Water and Refrigerant R245fa |
| No. 713 |
|
Uncertainty Analysis of Severe Accident Scenario in Krško NPP |
| Kořínek Tomáš |
| No. 115 |
|
Integration of Heat-only Small Modular Reactor with Thermally Driven Systems |
| No. 421 |
|
Experimental Investigation of Thermal Wave Flow Meter for Molten Salt Applications |
| Kos Leon |
| No. 1009 |
|
Divertor Armor Damage Estimation and Dynamics of Secondary Tungsten Plasma Simulation with TOKES in ITER |
| Kostanjevec Marko |
| No. 511 |
|
Challenges and Objectives in Managing Institutional Radioactive Waste in Slovenia |
| Koželj Matjaž |
| No. 205 |
|
Evaluation of the Justification for Using Consumer Products and Geological Samples Containing Radioactive Substances |
| Kramberger Gregor |
| No. 906 |
|
Fast neutron fluence profiling at the JSI TRIGA reactor irradiation facility |
| Kren Jan |
| No. 414 |
|
Bubble Breakup Sensitivity on Local Surface Tension Modification in LES of Turbulent Slug Flow |
| Kromar Marjan |
| No. 910 |
|
Intermediate range detectors for control rod worth measurements with rod insertion method |
| No. 918 |
|
An Analytical Model of Heat Transfer in a Fuel Rod Suitable for Neutron Calculations |
| No. 922 |
|
An overview of research project of the nuclear power plant load follow operation |
| Kromar Nejc |
| No. 702 |
|
Development of 3D fracture mechanics submodels for PTS analyses of an RPV with cracks |
| Krpan Rok |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| No. 420 |
|
RELAP5 Validation Against Experiment Performed in SIRIO Experimental Facility |
| Kudrnova Marie |
| No. 313 |
|
Corrosion behavior of materials in SCW environment |
| Kukhotskyi Oleksandr |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| Laks David |
| No. 902 |
|
Uncertainty Propagation of decay data for Decay Heat Calculations: A Monte Carlo Approach |
| Lame Jouybari Amirhossein |
| No. 308 |
|
ANALYSIS OF STRAIN LOCALIZATION IN IRRADIATED AUSTENITIC STAINLESS STEELS USING FFT-BASED CRYSTAL PLASTICITY SIMULATIONS |
| Lamour Antoine |
| No. 408 |
|
Experimental Investigation of Taylor Bubble Decay Rate in Counter-current flow |
| Leskovar Matjaž |
| No. 708 |
|
Modelling approach for premixing phase in combination of melt jet breakup and premixed layer formation of melt spread |
| No. 713 |
|
Uncertainty Analysis of Severe Accident Scenario in Krško NPP |
| Levpušček Blaž |
| No. 922 |
|
An overview of research project of the nuclear power plant load follow operation |
| Liegeard Clément |
| No. 412 |
|
Sensitivity analyses by a CFD model on water-wall behaviour in a LW SMR during SBO conditions |
| Lo Frano Rosa |
| No. 105 |
|
Preliminary feasibility study of coupling between SMR and desalination plant |
| Lodi Francesco |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| Löher Timo |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| Loi Lorenzo |
| No. 904 |
|
FEniCSx-OpenMC Coupling for Neutronic Calculation with Temperature Feedback |
| No. 912 |
|
OpenMC Analysis of TRIGA Mark II Reactor Void and Temperature Reactivity Coefficients |
| No. 916 |
|
OpenMC Model Validation of the TRIGA Mark II Reactor |
| Lokar Jan |
| No. 116 |
|
Potential Of Using SMR Reactors At Coal-Fired Power Plant Locations |
| Lombardi Carlo |
| No. 905 |
|
An Innovative Reactivity Control Strategy for Small Modular Reactors |
| Lorenzi Stefano |
| No. 912 |
|
OpenMC Analysis of TRIGA Mark II Reactor Void and Temperature Reactivity Coefficients |
| Lovasz Liviusz |
| No. 704 |
|
Simulation of an SBO accident in a PWR with AC2/ATHLET-CD with and without using ATF cladding material |
| Lovecky Martin |
| No. 921 |
|
Radiation Damage of SMR Reactor Vessel |
| No. 925 |
|
Calculation of Neutron and Electron Transport in Self-Powered Neutron Detector for PWR Fuel Assembly |
| No. 926 |
|
Neutronic modelling and computation of TEPLATOR core using COMSOL Multiphysics code |
| Lunardon Marcello |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Malec Jan |
| No. 917 |
|
Feasibility study for design and utilization of a cold neutron irradiation facility at the JSI TRIGA reactor |
| No. 922 |
|
An overview of research project of the nuclear power plant load follow operation |
| No. 924 |
|
Computer Programs Developed at Reactor Physics Department |
| Mandić Igor |
| No. 906 |
|
Fast neutron fluence profiling at the JSI TRIGA reactor irradiation facility |
| Marco Ferrero |
| No. 906 |
|
Fast neutron fluence profiling at the JSI TRIGA reactor irradiation facility |
| Marro Alejandro |
| No. 909 |
|
Possibility of using so-called “binary” “grey” control rods for power regulation of a nuclear reactor |
| Martin Tomas |
| No. 1007 |
|
Novel Methods of Isotopic Separation of Lithium 6 |
| Marušáková Daniela |
| No. 303 |
|
Stress corrosion cracking behavior of stainless steel 310S in supercritical water |
| No. 313 |
|
Corrosion behavior of materials in SCW environment |
| Matijević Mario |
| No. 202 |
|
Correlation Between Public Acceptance of Nuclear Technology and Trust in Scientists – Case Study Croatia |
| No. 612 |
|
The Assessment of Dose Rates during MPC Loading and Drying in frame of the Nuclear Power Plant Krško First SFDS Loading Campaign |
| Mazzini Guido |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| McCombie Charles |
| No. 502 |
|
How will backend issues affect the global deployment of SMRs? |
| Mechora Špela |
| No. 505 |
|
Updates on LILW disposal facility in Slovenia |
| Mede Timon |
| No. 302 |
|
Probabilistic assessment of induced intergranular stresses in polycrystalline materials |
| Megson-Smith David |
| No. 605 |
|
Enhanced Indoor Inspection of Nuclear Facilities through Non-Rigid Airship-Based SLAM System |
| Menezes Maria Angela de Barros Correia |
| No. 907 |
|
Influence of the temporal variability of neutron fluxes in the carousel of TRIGA Mark IPR-R1 research reactor, CDTN, Brazil, in the k0-method of neutron activation analysis |
| Merljak Vid |
| No. 501 |
|
Krško NPP Spent Fuel Dry Storage Project – Technology and Implementation Overview |
| Mihelčič Anže |
| No. 922 |
|
An overview of research project of the nuclear power plant load follow operation |
| Mihovilovič Miha |
| No. 710 |
|
Analysis of analogue data transmission of dose rate measurements over the HAM amateur radio network in the event of an emergency and possible failure of other communication channels |
| Mikuž Blaž |
| No. 408 |
|
Experimental Investigation of Taylor Bubble Decay Rate in Counter-current flow |
| No. 414 |
|
Bubble Breakup Sensitivity on Local Surface Tension Modification in LES of Turbulent Slug Flow |
| No. 416 |
|
The 3D DNS simulation of a Taylor bubble in counter-current flow with a turbulent wake using the Front-Tracking method in TrioCFD |
| No. 425 |
|
Measurement of Radiative Transport Properties of Water and Refrigerant R245fa |
| Mlakar Primož |
| No. 109 |
|
Nuclear Power Plant Cooling Tower Steam Emission Environmental Impact |
| MOLLA Yohannes |
| No. 902 |
|
Uncertainty Propagation of decay data for Decay Heat Calculations: A Monte Carlo Approach |
| Morselli Luca |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Mossini Eros |
| No. 517 |
|
Improved Geopolymers For Encapsulation Of Molten Salts From Thermal Treatment Processes |
| Moškon Milan |
| No. 604 |
|
On the reasons and extent of NEK's seismic instrumentation upgrade |
| Moura Rodrigo Reis |
| No. 907 |
|
Influence of the temporal variability of neutron fluxes in the carousel of TRIGA Mark IPR-R1 research reactor, CDTN, Brazil, in the k0-method of neutron activation analysis |
| Mühle Alexander |
| No. 509 |
|
Uncertainty of Fuel Assembly Burnup in Siemens/KWU PWRs |
| Nardoni Kovač Špela |
| No. 811 |
|
Renovation of the permanent exhibition on nuclear techology |
| Nemec Tomaž |
| No. 112 |
|
Role of Small Modular Reactors in the Future of Nuclear Power |
| Nguyen Thi Nhan |
| No. 515 |
|
Direct conditioning of liquid organic radioactive waste into a geopolymer matrix |
| Nitoi Mirela |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| Noguere Gilles |
| No. 928 |
|
Thermal Scattering Law for Zirconium Hydride |
| Nop Raksmy |
| No. 416 |
|
The 3D DNS simulation of a Taylor bubble in counter-current flow with a turbulent wake using the Front-Tracking method in TrioCFD |
| Novák Michal |
| No. 303 |
|
Stress corrosion cracking behavior of stainless steel 310S in supercritical water |
| Novotný Radek |
| No. 303 |
|
Stress corrosion cracking behavior of stainless steel 310S in supercritical water |
| Opraškar Rok |
| No. 710 |
|
Analysis of analogue data transmission of dose rate measurements over the HAM amateur radio network in the event of an emergency and possible failure of other communication channels |
| Padovani Enrico |
| No. 912 |
|
OpenMC Analysis of TRIGA Mark II Reactor Void and Temperature Reactivity Coefficients |
| Pandazis Peter |
| No. 704 |
|
Simulation of an SBO accident in a PWR with AC2/ATHLET-CD with and without using ATF cladding material |
| Panka István |
| No. 914 |
|
Burnup-dependent group constant parametrization by applying different machine learning methodologies |
| Papukchiev Angel |
| No. 812 |
|
Vibration impact in nuclear power generation: Go-viking advancements |
| Parduba Zbynek |
| No. 418 |
|
Simulation of PASI experiment on passive containment heat removal system with MELCOR and ATHLET |
| Pavel Gabriel Lazaro |
| No. 801 |
|
Impact of the ENEN2plus project after one year of implementation |
| No. 804 |
|
Towards Optimized Use of Research Reactors in Europe - Summary and Results |
| Perne Žiga |
| No. 408 |
|
Experimental Investigation of Taylor Bubble Decay Rate in Counter-current flow |
| Pestchanyi Sergey |
| No. 1009 |
|
Divertor Armor Damage Estimation and Dynamics of Secondary Tungsten Plasma Simulation with TOKES in ITER |
| Pesznyak Csilla |
| No. 801 |
|
Impact of the ENEN2plus project after one year of implementation |
| Petrović Bojan |
| No. 429 |
|
Usage of Monte Carlo Code Serpent2 for Calculation of FHR Fuel Assembly |
| Phung Quoc Tri |
| No. 515 |
|
Direct conditioning of liquid organic radioactive waste into a geopolymer matrix |
| Piliuhina Kateryna |
| No. 812 |
|
Vibration impact in nuclear power generation: Go-viking advancements |
| Piluso Pascal |
| No. 707 |
|
Experimental Measurements of Thermophysical Properties of Several Corium Compositions and Influence on Fuel-Coolant Interaction |
| Planquart Philippe |
| No. 812 |
|
Vibration impact in nuclear power generation: Go-viking advancements |
| Pleško Sebastian |
| No. 924 |
|
Computer Programs Developed at Reactor Physics Department |
| Pleterski Matej |
| No. 606 |
|
RPV threaded hole lubrication device |
| Ploj Tomaž |
| No. 107 |
|
Nuclear power plants as a solution for reducing carbon footprint and achieving sustainable energy system |
| Pražák Petr |
| No. 517 |
|
Improved Geopolymers For Encapsulation Of Molten Salts From Thermal Treatment Processes |
| Prošek Andrej |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| No. 401 |
|
TRACE Analysis of Total Loss of Feedwater in PWR |
| No. 417 |
|
Uncertainty and Sensitivity Analysis of Hot Leg Loss of Coolant Accident Simulated by RELAP5 |
| No. 420 |
|
RELAP5 Validation Against Experiment Performed in SIRIO Experimental Facility |
| No. 424 |
|
Loss of Coolant Accident with Total Failure of High Pressure Injection System in Two-loop PWR |
| No. 702 |
|
Development of 3D fracture mechanics submodels for PTS analyses of an RPV with cracks |
| Pucciarelli Andrea |
| No. 410 |
|
Extrapolating Phenomena Observed with Carbon Dioxide to Supercritical Water Reactor Conditions |
| Pungerčič Anže |
| No. 804 |
|
Towards Optimized Use of Research Reactors in Europe - Summary and Results |
| No. 913 |
|
Experimental and Computational Validation of Novel Depletion Algorithm in the RAPID Code System using JSI TRIGA reactor |
| Radulović Vladimir |
| No. 923 |
|
Jožef Stefan Institute TRIGA Research Reactor Activities in the Period from September 2022 – August 2023 |
| Ray Dipanjan |
| No. 926 |
|
Neutronic modelling and computation of TEPLATOR core using COMSOL Multiphysics code |
| Rejkova Jana |
| No. 313 |
|
Corrosion behavior of materials in SCW environment |
| Repetto Georges |
| No. 701 |
|
Fuel Cladding Deformation during LOCA: Comparaison between Single-rod and Multi-rod tests |
| Rimkevičius Sigitas |
| No. 1002 |
|
Licensing fusion facilities based on the ITER and DEMO paradigms |
| Riva Stefano |
| No. 904 |
|
FEniCSx-OpenMC Coupling for Neutronic Calculation with Temperature Feedback |
| No. 915 |
|
Multi-Physics Model Correction with Data-Driven Reduced Order Modelling |
| Rouge Emmanuel |
| No. 701 |
|
Fuel Cladding Deformation during LOCA: Comparaison between Single-rod and Multi-rod tests |
| Rupnik Sebastjan |
| No. 923 |
|
Jožef Stefan Institute TRIGA Research Reactor Activities in the Period from September 2022 – August 2023 |
| Ryan Tucker Matthew |
| No. 605 |
|
Enhanced Indoor Inspection of Nuclear Facilities through Non-Rigid Airship-Based SLAM System |
| Salvini Andrea |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Santi Andrea |
| No. 517 |
|
Improved Geopolymers For Encapsulation Of Molten Salts From Thermal Treatment Processes |
| Sapon Mykola |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| Schonfelder Christian |
| No. 801 |
|
Impact of the ENEN2plus project after one year of implementation |
| Schoop Sebastian |
| No. 504 |
|
Calculation method for determining neutron-induced nuclide activities in nuclear facilities |
| No. 509 |
|
Uncertainty of Fuel Assembly Burnup in Siemens/KWU PWRs |
| Scott Thomas Bligh |
| No. 1007 |
|
Novel Methods of Isotopic Separation of Lithium 6 |
| Scott Tom |
| No. 605 |
|
Enhanced Indoor Inspection of Nuclear Facilities through Non-Rigid Airship-Based SLAM System |
| No. 1013 |
|
Radiation Tolerant Neutron Activation Detector for Compact Inertial Electrostatically Confined Fusors |
| Sears Anna |
| No. 515 |
|
Direct conditioning of liquid organic radioactive waste into a geopolymer matrix |
| No. 517 |
|
Improved Geopolymers For Encapsulation Of Molten Salts From Thermal Treatment Processes |
| Sebestény Dániel |
| No. 914 |
|
Burnup-dependent group constant parametrization by applying different machine learning methodologies |
| Senegačnik Andrej |
| No. 117 |
|
Thermal Energy Storage Combined With a Molten Salt Reactor |
| Shyshuta Anatolii |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| Skobe Tomaž |
| No. 806 |
|
Basics of Nuclear Technology Courses in Nuclear Training Centre Ljubljana |
| No. 811 |
|
Renovation of the permanent exhibition on nuclear techology |
| Slapar Borišek Vesna |
| No. 811 |
|
Renovation of the permanent exhibition on nuclear techology |
| Slavič Slavko |
| No. 924 |
|
Computer Programs Developed at Reactor Physics Department |
| Smodiš Borut |
| No. 923 |
|
Jožef Stefan Institute TRIGA Research Reactor Activities in the Period from September 2022 – August 2023 |
| Snoj Luka |
| No. 906 |
|
Fast neutron fluence profiling at the JSI TRIGA reactor irradiation facility |
| No. 910 |
|
Intermediate range detectors for control rod worth measurements with rod insertion method |
| No. 913 |
|
Experimental and Computational Validation of Novel Depletion Algorithm in the RAPID Code System using JSI TRIGA reactor |
| No. 922 |
|
An overview of research project of the nuclear power plant load follow operation |
| No. 923 |
|
Jožef Stefan Institute TRIGA Research Reactor Activities in the Period from September 2022 – August 2023 |
| No. 928 |
|
Thermal Scattering Law for Zirconium Hydride |
| Sola Valentina |
| No. 906 |
|
Fast neutron fluence profiling at the JSI TRIGA reactor irradiation facility |
| Song Shanqi |
| No. 605 |
|
Enhanced Indoor Inspection of Nuclear Facilities through Non-Rigid Airship-Based SLAM System |
| Specchia Elisa |
| No. 109 |
|
Nuclear Power Plant Cooling Tower Steam Emission Environmental Impact |
| Starflinger Joerg |
| No. 402 |
|
Analysis of an innovative passive heat removal system for station blackout scenario |
| No. 804 |
|
Towards Optimized Use of Research Reactors in Europe - Summary and Results |
| Stefanova Antoaneta |
| No. 426 |
|
Comparison of the main parameters behavior in VVER 1000 during a MSLB accident for different fuel campaigns |
| Stepišnik Matjaž |
| No. 205 |
|
Evaluation of the Justification for Using Consumer Products and Geological Samples Containing Radioactive Substances |
| Sučić Simona |
| No. 511 |
|
Challenges and Objectives in Managing Institutional Radioactive Waste in Slovenia |
| Šadek Siniša |
| No. 422 |
|
Analysis of Steam Generator Tube Rupture (SGTR) Accident using RELAP5/MOD 3.3 and TRACE 5.0p5 Codes |
| No. 612 |
|
The Assessment of Dose Rates during MPC Loading and Drying in frame of the Nuclear Power Plant Krško First SFDS Loading Campaign |
| Šípová Monika |
| No. 303 |
|
Stress corrosion cracking behavior of stainless steel 310S in supercritical water |
| Škarohlid Jan |
| No. 108 |
|
A study of integration of Liquid Air Energy Storage (LAES) technology to nuclear district heating facility TEPLATOR |
| No. 421 |
|
Experimental Investigation of Thermal Wave Flow Meter for Molten Salt Applications |
| Škoda Radek |
| No. 108 |
|
A study of integration of Liquid Air Energy Storage (LAES) technology to nuclear district heating facility TEPLATOR |
| No. 115 |
|
Integration of Heat-only Small Modular Reactor with Thermally Driven Systems |
| No. 921 |
|
Radiation Damage of SMR Reactor Vessel |
| No. 925 |
|
Calculation of Neutron and Electron Transport in Self-Powered Neutron Detector for PWR Fuel Assembly |
| No. 926 |
|
Neutronic modelling and computation of TEPLATOR core using COMSOL Multiphysics code |
| Škrabec Franci |
| No. 606 |
|
RPV threaded hole lubrication device |
| Škugor Ferdebar Zdravka |
| No. 202 |
|
Correlation Between Public Acceptance of Nuclear Technology and Trust in Scientists – Case Study Croatia |
| Štrubelj Luka |
| No. 109 |
|
Nuclear Power Plant Cooling Tower Steam Emission Environmental Impact |
| Švajger Ingrid |
| No. 928 |
|
Thermal Scattering Law for Zirconium Hydride |
| Tarfila Patrik |
| No. 1005 |
|
Development of a Thermo-mechanical Model for DTT PFU |
| Taurines Tatiana |
| No. 701 |
|
Fuel Cladding Deformation during LOCA: Comparaison between Single-rod and Multi-rod tests |
| Tekavčič Matej |
| No. 415 |
|
A mechanistic bubble force model for the development of boiling parameters in high heat flux regimes |
| No. 425 |
|
Measurement of Radiative Transport Properties of Water and Refrigerant R245fa |
| Terranova Nicholas |
| No. 1002 |
|
Licensing fusion facilities based on the ITER and DEMO paradigms |
| Tinarelli Gianni |
| No. 109 |
|
Nuclear Power Plant Cooling Tower Steam Emission Environmental Impact |
| Tiselj Iztok |
| No. 414 |
|
Bubble Breakup Sensitivity on Local Surface Tension Modification in LES of Turbulent Slug Flow |
| No. 416 |
|
The 3D DNS simulation of a Taylor bubble in counter-current flow with a turbulent wake using the Front-Tracking method in TrioCFD |
| Tosato Marianna |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Trkov Andrej |
| No. 922 |
|
An overview of research project of the nuclear power plant load follow operation |
| No. 924 |
|
Computer Programs Developed at Reactor Physics Department |
| No. 928 |
|
Thermal Scattering Law for Zirconium Hydride |
| Trontl Krešimir |
| No. 202 |
|
Correlation Between Public Acceptance of Nuclear Technology and Trust in Scientists – Case Study Croatia |
| Tyson Sean |
| No. 502 |
|
How will backend issues affect the global deployment of SMRs? |
| Umminger Klaus |
| No. 407 |
|
Sensitivity studies on Reverse Natural Circulation in the PKL facility by using RELAP5 mod3.2mz |
| Urbonavičius Egidijus |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| No. 1002 |
|
Licensing fusion facilities based on the ITER and DEMO paradigms |
| Uršič Mitja |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| No. 708 |
|
Modelling approach for premixing phase in combination of melt jet breakup and premixed layer formation of melt spread |
| No. 713 |
|
Uncertainty Analysis of Severe Accident Scenario in Krško NPP |
| No. 1002 |
|
Licensing fusion facilities based on the ITER and DEMO paradigms |
| Vacek Martin |
| No. 517 |
|
Improved Geopolymers For Encapsulation Of Molten Salts From Thermal Treatment Processes |
| Vasiliev Alexander |
| No. 712 |
|
Advanced Analytical and Numerical Modelling of ATF FeCrAl and Cr-Coated Zr-Based Cladding High Temperature Oxidation in Steam Atmosphere |
| Verbelen Yannick |
| No. 605 |
|
Enhanced Indoor Inspection of Nuclear Facilities through Non-Rigid Airship-Based SLAM System |
| No. 1013 |
|
Radiation Tolerant Neutron Activation Detector for Compact Inertial Electrostatically Confined Fusors |
| Villa Valerio |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Viršek Sandi |
| No. 505 |
|
Updates on LILW disposal facility in Slovenia |
| No. 514 |
|
Deep Borehole Disposal as an Alternative Disposal Option for Spent Fuel |
| Vodopivec Janez |
| No. 511 |
|
Challenges and Objectives in Managing Institutional Radioactive Waste in Slovenia |
| Vyskocil Ladislav |
| No. 404 |
|
Application of CFD and system codes to simulation of HERO-2 experiment |
| Wang Xiang |
| No. 904 |
|
FEniCSx-OpenMC Coupling for Neutronic Calculation with Temperature Feedback |
| Wegrzynowski Norbert |
| No. 1007 |
|
Novel Methods of Isotopic Separation of Lithium 6 |
| Wielenberg Andreas |
| No. 206 |
|
Implementation and application of a GitLab CI-pipeline in support of V&V activities of AC2 |
| Zajec Boštjan |
| No. 209 |
|
On the applicability of the IAEA documentation to innovative reactors |
| No. 211 |
|
Design innovations and novel safety claims impacting power plant licensing |
| Zakšek Peter |
| No. 710 |
|
Analysis of analogue data transmission of dose rate measurements over the HAM amateur radio network in the event of an emergency and possible failure of other communication channels |
| Zangrando Lisa |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Závorka Jiří |
| No. 921 |
|
Radiation Damage of SMR Reactor Vessel |
| No. 925 |
|
Calculation of Neutron and Electron Transport in Self-Powered Neutron Detector for PWR Fuel Assembly |
| No. 926 |
|
Neutronic modelling and computation of TEPLATOR core using COMSOL Multiphysics code |
| Zenoni Aldo |
| No. 903 |
|
The ISOLPHARM project: 111Ag Production and separation at L.E.N.A. |
| Zingales Vincenzo |
| No. 407 |
|
Sensitivity studies on Reverse Natural Circulation in the PKL facility by using RELAP5 mod3.2mz |
| Zorko Benjamin |
| No. 710 |
|
Analysis of analogue data transmission of dose rate measurements over the HAM amateur radio network in the event of an emergency and possible failure of other communication channels |
| Zorko Domen |
| No. 606 |
|
RPV threaded hole lubrication device |
| Zupančič Kaja |
| No. 107 |
|
Nuclear power plants as a solution for reducing carbon footprint and achieving sustainable energy system |
| Zwijsen Kevin |
| No. 812 |
|
Vibration impact in nuclear power generation: Go-viking advancements |
| Žagar Tomaž |
| No. 107 |
|
Nuclear power plants as a solution for reducing carbon footprint and achieving sustainable energy system |
| No. 922 |
|
An overview of research project of the nuclear power plant load follow operation |
| Žefran Bojan |
| No. 924 |
|
Computer Programs Developed at Reactor Physics Department |
| Žerovnik Gašper |
| No. 909 |
|
Possibility of using so-called “binary” “grey” control rods for power regulation of a nuclear reactor |
| No. 917 |
|
Feasibility study for design and utilization of a cold neutron irradiation facility at the JSI TRIGA reactor |
| No. 918 |
|
An Analytical Model of Heat Transfer in a Fuel Rod Suitable for Neutron Calculations |
| No. 922 |
|
An overview of research project of the nuclear power plant load follow operation |
| Živko Tomi |
| No. 112 |
|
Role of Small Modular Reactors in the Future of Nuclear Power |
