|
|
Abushamah Hussein |
| No. 910 |
Optimization of Sizing and
Operation of a Nuclear District Heating System Using Teplator,
Gas Boiler and Heat Storage
|
| No. 1201 |
Nuclear power for the
decarbonization of the district heating sector in the Czech
Republic
|
|
Alfinito Federico |
| No. 303 |
Ageing Management Program revision
for the Pavia TRIGA MK II research reactor
|
|
Alloni Daniele |
| No. 303 |
Ageing Management Program revision
for the Pavia TRIGA MK II research reactor
|
|
Ambrožič Klemen |
| No. 305 |
New Research Reactor Developments
in Slovenia
|
| No. 509 |
Modelling gamma calorimetry
experiment with JSIR2S code
|
|
Angelucci Michela |
| No. 705 |
Thermal Modeling of SNF Behaviour
During Dry Storage: from 3D CFD to simple approaches
|
| No. 1110 |
Supervised Machine Learning-based
Feature Selection in the Frame of BEPU in Severe Accidents
|
|
Aquaro Donato |
| No. 1105 |
Influence of Non-Condensable
Gas-Dust Mixture on Direct Contact Condensation of Steam at
Atmospheric Pressure
|
|
Babka Lukáš |
| No. 609 |
Thick protective Fe and Mo coatings
for PbLi coolant environments prepared by RF-ICP and cold spray
|
|
Bachmann Christian |
| No. 1015 |
Natural convection cooling in DEMO
Vacuum Vessel during ex-VV LOCA
|
|
Bakr Arby Mahmoud |
| No. 1002 |
Design of an Automated System for
Electrolytic Fusion Fuel Implantation in Metallic Filaments
|
|
Barrick Erin |
| No. 613 |
Towards More Ductile Refractory
High-Entropy Alloys at Room Temperature
|
|
Basavaraj Anil Kumar |
| No. 308 |
Analysis of water activation loop
at the JSI TRIGA research reactor
|
| No. 413 |
Design optimization of heat
transfer performance in the heads of flow boiling experiment
|
|
Benčik Vesna |
| No. 519 |
Dose Rate Assessment around the
PCFV Release Line during Severe Accident Conditions in Nuclear
Power Plant Krsko
|
|
Bergant Robert |
| No. 1203 |
The Integration of Hybrid Nuclear
Renewable Energy Systems
|
|
Berti Luca |
| No. 1105 |
Influence of Non-Condensable
Gas-Dust Mixture on Direct Contact Condensation of Steam at
Atmospheric Pressure
|
|
Bestion Dominique |
| No. 417 |
Review of fonesys and silence nuclear thermal-hydraulic networks achievements
|
|
Bignan Gilles |
| No. 305 |
New Research Reactor Developments
in Slovenia
|
|
Bocanegra Rafael |
| No. 1110 |
Supervised Machine Learning-based
Feature Selection in the Frame of BEPU in Severe Accidents
|
|
Boccelli Riccardo |
| No. 311 |
Analysis of the void coefficient in
Pavia TRIGA Mark-II reactor: Monte Carlo numerical evaluation
and comparison with experimental data
|
|
Boeck Prof.Dr. Helmuth |
| No. 206 |
Nuclear Education – what influence
does online teaching have – a cause study in Austria
|
| No. 304 |
The European Nuclear Experimental
Educational Platform – ENEEP: Overview and Demonstration
Activities
|
|
Bogdanović Leon |
| No. 1014 |
Towards refactoring of the TOKES
tokamak plasma transient code
|
|
Brega Vittoria |
| No. 306 |
Dynamic Mode Decomposition Analysis
of a Cooling Channel of the TRIGA Mark II Reactor
|
|
Breitung Wolfgang |
| No. 1104 |
Experiments on radiolysis gas
detonation in BWR exhaust pipes and mechanical response to the
detonation pressure loads
|
|
Burian Ondřej |
| No. 409 |
Thermal-hydraulic analysis of
TEPLATOR moderator cooling system
|
|
Cabezas Marcos |
| No. 903 |
Application of flex strategies to cope with a station blackout (SBO) situation
|
| No. 1101 |
Analysis of the impact of some post-Fukushima improvements in design extension conditions sequences
|
| No. 1108 |
Application of the generic and specific SPAR-CSN probabilistic safety assessment models to several incidents
|
|
Cagnazzo Marcella |
| No. 304 |
The European Nuclear Experimental
Educational Platform – ENEEP: Overview and Demonstration
Activities
|
|
Cai Qingling |
| No. 416 |
Review of application of FFTBM method for code accuracy quantification
|
| No. 417 |
Review of fonesys and silence nuclear thermal-hydraulic networks achievements
|
|
Calabrese Rolando |
| No. 605 |
Heat Capacity of PuO2 at High
Temperature: a comparison of interatomic potentials
|
| No. 606 |
Crystallographic phase transition
of zirconium alloys: new models for the TRANSURANUS code
|
|
Cammi Antonio |
| No. 306 |
Dynamic Mode Decomposition Analysis of a Cooling
Channel of the TRIGA Mark II Reactor
|
| No. 311 |
Analysis of the void coefficient in Pavia TRIGA Mark-II reactor:
Monte Carlo numerical evaluation and comparison with
experimental data
|
| No. 405 |
Multiphysics Analysis of an in-core Fission Product Removal
System for the Molten Salt Fast Reactor
|
| No. 415 |
Inviscid fluid simulation through Incompressible Schrödinger
Flow method: a Finite Element approach
|
| No. 518 |
A Monte Carlo fuel assembly model validation adopting Post
Irradiation Experiment dataset
|
| Cancemi Salvatore Angelo |
| No. 708 |
Numerical Simulation Of Cemented RLOW For
Packaging System
|
| No. 906 |
Unsupervised ML anomaly detection approach for NPPs LTO Program
|
|
Carcreff Hubert |
| No. 509 |
Modelling gamma calorimetry experiment with
JSIR2S code
|
|
Ciattaglia Sergio |
| No. 1015 |
Natural convection cooling in DEMO Vacuum Vessel
during ex-VV LOCA
|
|
Cirillo Roberta |
| No. 202 |
ENEN2plus, Building European Nuclear Competence
through continuous Advanced and Structured
Education and Training Actions
|
|
Cizek Jan |
| No. 609 |
Thick protective Fe and Mo coatings for PbLi
coolant environments prepared by RF-ICP and cold
spray
|
|
Cizelj Leon |
| No. 406 |
Experimental study on bubble size distributions
in horizontal narrow-gap annular heat exchanger
|
| No. 603 |
Strain localization in austenitic stainless steel due to
hydrogen concentration
|
| No. 607 |
Development of a 3D-RPV Finite Element Model for Pressurized
Thermal Shock Analyses
|
|
Costa Garrido Oriol |
| No. 607 |
Development of a 3D-RPV Finite Element Model for
Pressurized Thermal Shock Analyses
|
| No. 1012 |
Development of a Thermohydraulic Model for DTT PFU
|
|
Courtin Sergio |
| No. 903 |
Application of flex strategies to cope with a station blackout (SBO) situation
|
| No. 1101 |
Analysis of the impact of some post-Fukushima improvements in design extension conditions sequences
|
| No. 1108 |
Application of the generic and specific SPAR-CSN probabilistic safety assessment models to several incidents
|
|
Czifrus Szabolcs |
| No. 304 |
The European Nuclear Experimental Educational
Platform – ENEEP: Overview and Demonstration
Activities
|
|
Čalič Dušan |
| No. 517 |
On the effective fuel temperature of the UO2
fuel
|
| No. 911 |
Simulation of load following operation with a PWR reactor
|
|
Čerba Štefan |
| No. 304 |
The European Nuclear Experimental Educational
Platform – ENEEP: Overview and Demonstration
Activities
|
| No. 501 |
The Definition of Mini Labyrinth Benchmark for Radiation
Shielding Calculations
|
|
Češarek Janez |
| No. 806 |
Safeguards-Related Activities in Slovenia since
2000 – Some Outcomes in a Nutshell and a Quick
Look Forward
|
|
Črne Primož |
| No. 1015 |
Natural convection cooling in DEMO Vacuum Vessel
during ex-VV LOCA
|
|
Čufar Aljaž |
| No. 1008 |
STOK – a tool for parametric modelling of simple
tokamaks
|
| No. 1009 |
Towards automation of fusion reactor design optimization –
neutronic optimization in simple parametric models
|
|
D Auria Francesco |
| No. 416 |
Review of application of FFTBM method for code accuracy quantification
|
| No. 417 |
Review of fonesys and silence nuclear thermal-hydraulic networks achievements
|
| Darnowski Piotr |
| No. 1204 |
Development of the MATLAB Tool for Optimization
of the Nuclear Hybrid Energy System Dedicated
for Hydrogen Production
|
|
Debelak Klemen |
| No. 410 |
Passive Isolation Condenser Modeling With Apros
Computer Code
|
| No. 1203 |
The Integration of Hybrid Nuclear Renewable Energy Systems
|
|
Denk Lubomir |
| No. 1107 |
Effect of sump pH on iodine release from
VVER-1000/V-320 containment during LB LOCA
|
|
Destouches Christophe |
| No. 305 |
New Research Reactor Developments in Slovenia
|
|
Dolin Viktor |
| No. 708 |
Numerical Simulation Of Cemented RLOW For
Packaging System
|
|
Dose Giacomo |
| No. 1012 |
Development of a Thermohydraulic Model for DTT
PFU
|
| Dossantos-Uzarralde Pierre-Jacques |
| No. 506 |
Application of machine learning to interpolation
and evaluation of delayed-neutron multiplicity
|
|
Draksler Martin |
| No. 1011 |
Simulation of Natural Convection in DEMO
Cryostat During Helium Ingress Accident
|
| No. 1015 |
Natural convection cooling in DEMO Vacuum Vessel during ex-VV
LOCA
|
|
Dučkić Paulina |
| No. 519 |
Dose Rate Assessment around the PCFV Release
Line during Severe Accident Conditions in
Nuclear Power Plant Krsko
|
| No. 706 |
Estimation of Dose Rates around Dry Storage Building during
Campaign One Loading in Nuclear Power Plant Krsko
|
|
Duhovnik Boštjan |
| No. 707 |
Development of the Vrbina LILW Repository Design
|
|
El Shawish Samir |
| No. 603 |
Strain localization in austenitic stainless
steel due to hydrogen concentration
|
| No. 610 |
Comparing different approaches to intergranular-stress modelling
|
|
Fathi Nima |
| No. 418 |
Thermal efficiency of protective cladding layers
in liquid sodium-cooled heat sinks containing
sharp corners
|
| No. 613 |
Towards More Ductile Refractory High-Entropy Alloys at Room
Temperature
|
| No. 1103 |
Importance of Physics-aware Use
of Area Validation Metric for LES Methanol Pool Fire Simulation Data
|
|
Feria Francisco |
| No. 705 |
Thermal Modeling of SNF Behaviour During Dry
Storage: from 3D CFD to simple approaches
|
|
Fernández-Cosials Kevin |
| No. 402 |
Thermal-Hydraulic Analysis of the 2nd Stage
Hydroaccumulators Impact in MB/LBLOCA Sequences
along with SBO
|
|
Filova Vendula |
| No. 501 |
The Definition of Mini Labyrinth Benchmark for
Radiation Shielding Calculations
|
|
Fleming Darryn |
| No. 613 |
Towards More Ductile Refractory High-Entropy
Alloys at Room Temperature
|
|
Forgione Nicola |
| No. 403 |
CFD Simulation of a VVER-1000/320 at Nominal
Operating Conditions
|
|
Foster David |
| No. 602 |
PATHFINDER: A tool for calculating pathways for
fusion-activated materials
|
|
Fourmentel Damien |
| No. 509 |
Modelling gamma calorimetry experiment with
JSIR2S code
|
|
Gabrijel Anže |
| No. 1008 |
STOK – a tool for parametric modelling of simple
tokamaks
|
| No. 1009 |
Towards automation of fusion reactor design optimization –
neutronic optimization in simple parametric models
|
|
Galek Vojtěch |
| No. 608 |
Direct conditioning of molten salt arising from
the thermal treatment of solid organic waste
|
|
Gandini Andrea |
| No. 303 |
Ageing Management Program revision for the Pavia
TRIGA MK II research reactor
|
|
García-Herranz Alberto |
| No. 903 |
Application of flex strategies to cope with a station blackout (SBO) situation
|
| No. 1101 |
Analysis of the impact of some post-Fukushima improvements in design extension conditions sequences
|
| No. 1108 |
Application of the generic and specific SPAR-CSN probabilistic safety assessment models to several incidents
|
|
Gerbelova Hana |
| No. 803 |
Measuring Social Impacts of Nuclear Closure and
Decommissioning
|
|
Giambartolomei Guglielmo |
| No. 1105 |
Influence of Non-Condensable Gas-Dust Mixture on
Direct Contact Condensation of Steam at
Atmospheric Pressure
|
|
Gilbert Mark |
| No. 602 |
PATHFINDER: A tool for calculating pathways for
fusion-activated materials
|
|
Giordano Michelangelo |
| No. 303 |
Ageing Management Program revision for the Pavia
TRIGA MK II research reactor
|
|
Giorgetti Francesco |
| No. 1012 |
Development of a Thermohydraulic Model for DTT
PFU
|
|
Glöde Helmut |
| No. 508 |
Our Experiences with the Benchmark “Rostov-2”
|
|
Goričanec Tanja |
| No. 507 |
On the calculation of adjoint neutron flux in
typical PWR for the determination of the neutron
flux redistribution factors
|
|
Grgić Davor |
| No. 519 |
Dose Rate Assessment around the PCFV Release
Line during Severe Accident Conditions in
Nuclear Power Plant Krsko
|
| No. 706 |
Estimation of Dose Rates around Dry Storage Building during
Campaign One Loading in Nuclear Power Plant Krsko
|
| No. 1117 |
Calculation of the QUENCH-02 experiment with the ASYST code
including the uncertainty evaluation
|
|
Grune Joachim |
| No. 1104 |
Experiments on radiolysis gas detonation in BWR
exhaust pipes and mechanical response to the
detonation pressure loads
|
|
Gueldner Manuel |
| No. 902 |
Reliability Analyses of Emergency Power Systems
with focus on Multi-Group Diesel Configurations
|
|
Hadrava Jan |
| No. 608 |
Direct conditioning of molten salt arising from
the thermal treatment of solid organic waste
|
|
Haendel Kai-Martin |
| No. 508 |
Our Experiences with the Benchmark “Rostov-2”
|
|
Haghighat Alireza |
| No. 510 |
Burnup measurements using fuel reactivity worth
experiments at the JSI TRIGA Research Reactor
|
|
Halim Ossama |
| No. 403 |
CFD Simulation of a VVER-1000/320 at Nominal
Operating Conditions
|
|
Haščík Ján |
| No. 304 |
The European Nuclear Experimental Educational
Platform – ENEEP: Overview and Demonstration
Activities
|
|
Házi Gábor |
| No. 401 |
SURET is a new form of subchannel
thermohydraulic calculations
|
|
Herranz Luis E. |
| No. 705 |
Thermal Modeling of SNF Behaviour During Dry
Storage: from 3D CFD to simple approaches
|
| No. 1110 |
Supervised Machine Learning-based Feature Selection in the Frame
of BEPU in Severe Accidents
|
|
Herrero-Otero Julia |
| No. 903 |
Application of flex strategies to cope with a station blackout (SBO) situation
|
| No. 1101 |
Analysis of the impact of some post-Fukushima improvements in design extension conditions sequences
|
| No. 1108 |
Application of the generic and specific SPAR-CSN probabilistic safety assessment models to several incidents
|
|
Hjalmarsson Anders |
| No. 1003 |
Cross-section analysis for neutron producing
fusion reactions in pre-fusion power operation
of the ITER tokamak
|
|
Horváth Csaba |
| No. 401 |
SURET is a new form of subchannel
thermohydraulic calculations
|
|
Horváth Márton |
| No. 401 |
SURET is a new form of subchannel
thermohydraulic calculations
|
|
Iglesias Rafael |
| No. 1108 |
Application of the generic and specific SPAR-CSN probabilistic safety assessment models to several incidents
|
|
Introini Carolina |
| No. 306 |
Dynamic Mode Decomposition Analysis of a Cooling
Channel of the TRIGA Mark II Reactor
|
| No. 311 |
Analysis of the void coefficient in Pavia TRIGA Mark-II reactor:
Monte Carlo numerical evaluation and comparison with
experimental data
|
| No. 405 |
Multiphysics Analysis of an in-core Fission Product Removal
System for the Molten Salt Fast Reactor
|
| No. 415 |
Inviscid fluid simulation through Incompressible Schrödinger
Flow method: a Finite Element approach
|
|
Istenič Radko |
| No. 808 |
Public Opinion about Nuclear Energy – Year 2022
Poll
|
|
Ivanjko Karlo |
| No. 1117 |
Calculation of the QUENCH-02 experiment with the
ASYST code including the uncertainty evaluation
|
|
Jacqmin Robert |
| No. 305 |
New Research Reactor Developments in Slovenia
|
|
Jazbec Anže |
| No. 304 |
The European Nuclear Experimental Educational
Platform – ENEEP: Overview and Demonstration
Activities
|
| No. 305 |
New Research Reactor Developments in Slovenia
|
| No. 310 |
Jožef Stefan Institute TRIGA Research Reactor Activities in the
Period from September 2021 – August 2022
|
|
Jazbinšek Jure |
| No. 805 |
Common misconceptions about nuclear energy - case study from interactions in visitors center
|
| No. 905 |
Production of hydrogen and synthetic methane with nuclear power plants
|
|
Ječmenica Radomir |
| No. 706 |
Estimation of Dose Rates around Dry Storage
Building during Campaign One Loading in Nuclear
Power Plant Krsko
|
|
Jenčič Igor |
| No. 808 |
Public Opinion about Nuclear Energy – Year 2022
Poll
|
|
Jimenez Gonzalo |
| No. 404 |
Scaling down of PWR nuclear power plant
secondary side for SIRIO experimental facility
supported by system thermal-hydraulic codes
|
|
Jiřičková Jana |
| No. 513 |
Moderator Heat Sources in TEPLATOR District
Heating SMR
|
| No. 910 |
Optimization of Sizing and Operation of a Nuclear District
Heating System Using Teplator, Gas Boiler and Heat Storage
|
| No. 1201 |
Nuclear power for the decarbonization of the district heating
sector in the Czech Republic
|
|
Jockenhövel-Barttfeld Mariana |
| No. 902 |
Reliability Analyses of Emergency Power Systems
with focus on Multi-Group Diesel Configurations
|
|
Kálya Zoltán |
| No. 401 |
SURET is a new form of subchannel
thermohydraulic calculations
|
|
Kanth Priti |
| No. 602 |
PATHFINDER: A tool for calculating pathways for
fusion-activated materials
|
|
Kaszko Aleksej |
| No. 1111 |
Application of dynamic bayesian network in
initiating event calculation
|
|
Kecek Adam |
| No. 1107 |
Effect of sump pH on iodine release from
VVER-1000/V-320 containment during LB LOCA
|
|
Kekec Aljaž |
| No. 407 |
Simulation of flow in PWR reactor pressure
vessel downcomer
|
|
Kirsch Jared |
| No. 1103 |
Importance of Physics-aware Use
of Area Validation Metric for LES Methanol Pool Fire Simulation Data
|
|
Klecka Jakub |
| No. 609 |
Thick protective Fe and Mo coatings for PbLi
coolant environments prepared by RF-ICP and cold
spray
|
|
Kljenak Ivo |
| No. 404 |
Scaling down of PWR nuclear power plant
secondary side for SIRIO experimental facility
supported by system thermal-hydraulic codes
|
| No. 407 |
Simulation of flow in PWR reactor pressure vessel downcomer
|
|
Kodeli Ivan |
| No. 506 |
Application of machine learning to interpolation
and evaluation of delayed-neutron multiplicity
|
|
Kokalj Janez |
| No. 1010 |
Analysis of Large Helium Ingress into the DEMO
Cryostat Using MELCOR for Fusion
|
| No. 1106 |
Analysis of Influence of DEC Equipment on Severe Accident
Development
|
| No. 1115 |
Simulation of fuel-coolant interaction in stratified
configuration in reactor geometry
|
|
Končar Boštjan |
| No. 406 |
Experimental study on bubble size distributions
in horizontal narrow-gap annular heat exchanger
|
| No. 1010 |
Analysis of Large Helium Ingress into the DEMO Cryostat Using
MELCOR for Fusion
|
| No. 1012 |
Development of a Thermohydraulic Model for DTT PFU
|
| No. 1015 |
Natural convection cooling in DEMO Vacuum Vessel during ex-VV
LOCA
|
|
Končar Mihael Boštjan |
| No. 414 |
Application of enhanced phase-change model for
simulation of film boiling around a cylinder
|
|
Kopka Piotr |
| No. 1111 |
Application of dynamic bayesian network in
initiating event calculation
|
|
Kořínek Tomáš |
| No. 409 |
Thermal-hydraulic analysis of TEPLATOR moderator
cooling system
|
| No. 513 |
Moderator Heat Sources in TEPLATOR District Heating SMR
|
| No. 909 |
Seasonal and daily operation of nuclear based district heating
system with varying energy demand
|
|
Kos Leon |
| No. 1013 |
Kinetic Effects in ITER Scrape-off Layer
|
| No. 1014 |
Towards refactoring of the TOKES tokamak plasma transient code
|
|
Kosinac Garsia |
| No. 805 |
Common misconceptions about nuclear energy - case study from interactions in visitors center
|
|
Kotnik Domen |
| No. 308 |
Analysis of water activation loop at the JSI
TRIGA research reactor
|
|
Koželj Matjaž |
| No. 807 |
Background of Values Used for Exclusion,
Exemption and Clearance of Practices and Sources
from Regulatory Control
|
|
Kren Jan |
| No. 412 |
Analysis of bubble breakup sensitivity on fluid
properties using Large Eddy Simulations
|
|
Kromar Marjan |
| No. 507 |
On the calculation of adjoint neutron flux in
typical PWR for the determination of the neutron
flux redistribution factors
|
| No. 517 |
On the effective fuel temperature of the UO2 fuel
|
| No. 912 |
Modernization of the Fuel Assembly Register Software
|
|
Kromar Nejc |
| No. 607 |
Development of a 3D-RPV Finite Element Model for
Pressurized Thermal Shock Analyses
|
|
Krpan Rok |
| No. 404 |
Scaling down of PWR nuclear power plant
secondary side for SIRIO experimental facility
supported by system thermal-hydraulic codes
|
| No. 1010 |
Analysis of Large Helium Ingress into the DEMO Cryostat Using
MELCOR for Fusion
|
| No. 1011 |
Simulation of Natural Convection in DEMO Cryostat During Helium
Ingress Accident
|
|
Krull Benjamin |
| No. 408 |
Simulation of Liquid Waves With Flow Reversal in
Stratified Counter-Current Flow With a Hybrid
Multi-Fluid Model
|
|
Kubiński Wojciech |
| No. 1204 |
Development of the MATLAB Tool for Optimization
of the Nuclear Hybrid Energy System Dedicated
for Hydrogen Production
|
|
Kustas Andrew |
| No. 613 |
Towards More Ductile Refractory High-Entropy
Alloys at Room Temperature
|
|
Kuznetsov Mikhail |
| No. 1104 |
Experiments on radiolysis gas detonation in BWR
exhaust pipes and mechanical response to the
detonation pressure loads
|
|
Lame Jouybari Amirhossein |
| No. 603 |
Strain localization in austenitic stainless
steel due to hydrogen concentration
|
|
Lanfredini Marco |
| No. 417 |
Review of fonesys and silence nuclear thermal-hydraulic networks achievements
|
|
Lang Eric |
| No. 613 |
Towards More Ductile Refractory High-Entropy
Alloys at Room Temperature
|
|
Langegger Eileen |
| No. 206 |
Nuclear Education – what influence does online
teaching have – a cause study in Austria
|
|
Larriba Samantha |
| No. 404 |
Scaling down of PWR nuclear power plant
secondary side for SIRIO experimental facility
supported by system thermal-hydraulic codes
|
|
Lengar Igor |
| No. 308 |
Analysis of water activation loop at the JSI
TRIGA research reactor
|
|
Lenošek Kavčič Melita |
| No. 805 |
Common misconceptions about nuclear energy - case study from interactions in visitors center
|
|
Leskovar Matjaž |
| No. 1010 |
Analysis of Large Helium Ingress into the DEMO
Cryostat Using MELCOR for Fusion
|
| No. 1106 |
Analysis of Influence of DEC Equipment on Severe Accident
Development
|
| No. 1115 |
Simulation of fuel-coolant interaction in stratified
configuration in reactor geometry
|
|
Levpušček Blaž |
| No. 511 |
Maximum required excess reactivity due to Xe-135
“poisoning”
|
|
Lo Frano Rosa |
| No. 708 |
Numerical Simulation Of Cemented RLOW For
Packaging System
|
| No. 906 |
Unsupervised ML anomaly detection approach for NPPs LTO Program
|
|
Lo Muzio Silvia |
| No. 504 |
Implementation and validation of the steady
state SP3 approximation in the GRS FENNECS code
|
|
Loi Lorenzo |
| No. 518 |
A Monte Carlo fuel assembly model validation
adopting Post Irradiation Experiment dataset
|
|
Lokar Jan |
| No. 1203 |
The Integration of Hybrid Nuclear Renewable
Energy Systems
|
|
Lorenzi Stefano |
| No. 311 |
Analysis of the void coefficient in Pavia TRIGA
Mark-II reactor: Monte Carlo numerical
evaluation and comparison with experimental data
|
| No. 405 |
Multiphysics Analysis of an in-core Fission Product Removal
System for the Molten Salt Fast Reactor
|
| No. 518 |
A Monte Carlo fuel assembly model validation adopting Post
Irradiation Experiment dataset
|
|
Lovecký Martin |
| No. 409 |
Thermal-hydraulic analysis of TEPLATOR moderator
cooling system
|
| No. 513 |
Moderator Heat Sources in TEPLATOR District Heating SMR
|
| No. 515 |
Calculation and verification of the new neutron absorbers in a
well-defined core in LR-0 reactor
|
|
Lüley Jakub |
| No. 304 |
The European Nuclear Experimental Educational
Platform – ENEEP: Overview and Demonstration
Activities
|
| No. 501 |
The Definition of Mini Labyrinth Benchmark for Radiation
Shielding Calculations
|
|
Maksic Milos |
| No. 913 |
Dynamic Electrical Simulation Model of NPP Krsko
|
|
Malec Jan |
| No. 305 |
New Research Reactor Developments in Slovenia
|
|
Marn Jure |
| No. 407 |
Simulation of flow in PWR reactor pressure
vessel downcomer
|
|
Mašata David |
| No. 910 |
Optimization of Sizing and Operation of a
Nuclear District Heating System Using Teplator,
Gas Boiler and Heat Storage
|
| No. 1201 |
Nuclear power for the decarbonization of the
district heating sector in the Czech Republic
|
|
Matijević Mario |
| No. 706 |
Estimation of Dose Rates around Dry Storage
Building during Campaign One Loading in Nuclear
Power Plant Krsko
|
|
Mede Timon |
| No. 610 |
Comparing different approaches to
intergranular-stress modelling
|
|
Meléndez Asensio Enrique |
| No. 1101 |
Analysis of the impact of some post-Fukushima improvements in design extension conditions sequences
|
| No. 1108 |
Application of the generic and specific SPAR-CSN probabilistic safety assessment models to several incidents
|
|
Meller Richard |
| No. 408 |
Simulation of Liquid Waves With Flow Reversal in
Stratified Counter-Current Flow With a Hybrid
Multi-Fluid Model
|
|
Mendizábal Rafael |
| No. 1101 |
Analysis of the impact of some post-Fukushima improvements in design extension conditions sequences
|
|
Merljak Vid |
| No. 915 |
Resampling a Detailed Reactor Power History With
the Cycle Power History Script
|
|
Miglierini Marcel |
| No. 304 |
The European Nuclear Experimental Educational
Platform – ENEEP: Overview and Demonstration
Activities
|
|
Mikuž Blaž |
| No. 412 |
Analysis of bubble breakup sensitivity on fluid
properties using Large Eddy Simulations
|
| No. 413 |
Design optimization of heat transfer performance in the heads of
flow boiling experiment
|
|
Momirovski Aleksandar |
| No. 913 |
Dynamic Electrical Simulation Model of NPP Krsko
|
|
Monroe Graham |
| No. 613 |
Towards More Ductile Refractory High-Entropy
Alloys at Room Temperature
|
|
Moretti Fabio |
| No. 417 |
Review of fonesys and silence nuclear thermal-hydraulic networks achievements
|
|
Moscato Ivo |
| No. 1015 |
Natural convection cooling in DEMO Vacuum Vessel
during ex-VV LOCA
|
|
Nečas Vladimir |
| No. 501 |
The Definition of Mini Labyrinth Benchmark for
Radiation Shielding Calculations
|
|
Nemec Tomaž |
| No. 802 |
Regulatory Requirements for Siting of New
Slovenian NPP
|
|
Novak Ondrej |
| No. 304 |
The European Nuclear Experimental Educational
Platform – ENEEP: Overview and Demonstration
Activities
|
|
Oberlander Elina |
| No. 508 |
Our Experiences with the Benchmark “Rostov-2”
|
|
Oder Jure |
| No. 404 |
Scaling down of PWR nuclear power plant
secondary side for SIRIO experimental facility
supported by system thermal-hydraulic codes
|
|
Paci Sandro |
| No. 705 |
Thermal Modeling of SNF Behaviour During Dry
Storage: from 3D CFD to simple approaches
|
| No. 1110 |
Supervised Machine Learning-based Feature Selection in the Frame
of BEPU in Severe Accidents
|
|
París Carlos |
| No. 1108 |
Application of the generic and specific SPAR-CSN probabilistic safety assessment models to several incidents
|
|
Parkó Tamás |
| No. 401 |
SURET is a new form of subchannel
thermohydraulic calculations
|
|
Pavel Gabriel Lazaro |
| No. 202 |
ENEN2plus, Building European Nuclear Competence
through continuous Advanced and Structured
Education and Training Actions
|
|
Pavlinac Renato |
| No. 1117 |
Calculation of the QUENCH-02 experiment with the
ASYST code including the uncertainty evaluation
|
|
Peltan Tomáš |
| No. 516 |
Neutronic Analysis of Various Fuels for the
TEPLATOR HT
|
| No. 1202 |
Special experimental environment for Gen. IV reactors with
graphite reflector
|
|
Penalva Jaime |
| No. 705 |
Thermal Modeling of SNF Behaviour During Dry
Storage: from 3D CFD to simple approaches
|
|
Pesetti Alessio |
| No. 1105 |
Influence of Non-Condensable Gas-Dust Mixture on
Direct Contact Condensation of Steam at
Atmospheric Pressure
|
|
Pestchanyi Sergey |
| No. 1014 |
Towards refactoring of the TOKES tokamak plasma
transient code
|
|
Pesznyák Csilla |
| No. 202 |
ENEN2plus, Building European Nuclear Competence
through continuous Advanced and Structured
Education and Training Actions
|
|
Pleško Sebastian |
| No. 912 |
Modernization of the Fuel Assembly Register
Software
|
|
Pós István |
| No. 401 |
SURET is a new form of subchannel
thermohydraulic calculations
|
|
Pourghasemi Mahyar |
| No. 418 |
Thermal efficiency of protective cladding layers
in liquid sodium-cooled heat sinks containing
sharp corners
|
|
Pražák Petr |
| No. 608 |
Direct conditioning of molten salt arising from
the thermal treatment of solid organic waste
|
|
Prošek Andrej |
| No. 607 |
Development of a 3D-RPV Finite Element Model for
Pressurized Thermal Shock Analyses
|
| No. 1112 |
RELAP5 Simulations of Total Loss of Feedwater in a PWR
|
|
Pucciarelli Andrea |
| No. 403 |
CFD Simulation of a VVER-1000/320 at Nominal
Operating Conditions
|
|
Pungerčič Anže |
| No. 305 |
New Research Reactor Developments in Slovenia
|
| No. 510 |
Burnup measurements using fuel reactivity worth experiments at
the JSI TRIGA Research Reactor
|
|
Queral César |
| No. 402 |
Thermal-Hydraulic Analysis of the 2nd Stage
Hydroaccumulators Impact in MB/LBLOCA Sequences
along with SBO
|
| No. 404 |
Scaling down of PWR nuclear power plant secondary side for SIRIO
experimental facility supported by system thermal-hydraulic
codes
|
| No. 903 |
Application of flex strategies to cope with a station blackout (SBO) situation
|
| No. 1101 |
Analysis of the impact of some post-Fukushima improvements in design extension conditions sequences
|
| No. 1108 |
Application of the generic and specific SPAR-CSN probabilistic safety assessment models to several incidents
|
|
Radenac Erwan |
| No. 501 |
The Definition of Mini Labyrinth Benchmark for
Radiation Shielding Calculations
|
| Radulović Vladimir |
| No. 304 |
The European Nuclear Experimental Educational
Platform – ENEEP: Overview and Demonstration
Activities
|
| No. 305 |
New Research Reactor Developments in Slovenia
|
| No. 310 |
Jožef Stefan Institute TRIGA Research Reactor Activities in the
Period from September 2021 – August 2022
|
| No. 312 |
Testing of Silicon Carbide Neutron Detector for Detection of
Fast Neutrons
|
| No. 509 |
Modelling gamma calorimetry experiment with JSIR2S code
|
|
Raucci Michele |
| No. 1105 |
Influence of Non-Condensable Gas-Dust Mixture on
Direct Contact Condensation of Steam at
Atmospheric Pressure
|
|
Redlinger Reinhard |
| No. 1104 |
Experiments on radiolysis gas detonation in BWR
exhaust pipes and mechanical response to the
detonation pressure loads
|
|
Redondo-Valero Elena |
| No. 404 |
Scaling down of PWR nuclear power plant
secondary side for SIRIO experimental facility
supported by system thermal-hydraulic codes
|
| No. 402 |
Thermal-Hydraulic Analysis of the 2nd Stage
Hydroaccumulators Impact in MB/LBLOCA Sequences
along with SBO
|
|
Režonja Gumpot Benja |
| No. 802 |
Regulatory Requirements for Siting of New
Slovenian NPP
|
|
Riva Stefano |
| No. 415 |
Inviscid fluid simulation through Incompressible
Schrödinger Flow method: a Finite Element
approach
|
|
Rob Sharpe |
| No. 613 |
Towards More Ductile Refractory High-Entropy
Alloys at Room Temperature
|
|
Roccella Selanna |
| No. 1012 |
Development of a Thermohydraulic Model for DTT
PFU
|
|
Rocher Muriel |
| No. 701 |
Deep Borehole Repository of HLW and SF - State
of knowledge by SITEX.Network
|
|
Rodriguez Salvador |
| No. 613 |
Towards More Ductile Refractory High-Entropy
Alloys at Room Temperature
|
|
Rupnik Sebastjan |
| No. 310 |
Jožef Stefan Institute TRIGA Research Reactor
Activities in the Period from September 2021 –
August 2022
|
|
Ryan Tucker Matthew |
| No. 302 |
Radioactive environment characterisation using
multi detector arrays and a 3-dimensional
scanning Lidar
|
|
Sakho Abdoulaye |
| No. 506 |
Application of machine learning to interpolation
and evaluation of delayed-neutron multiplicity
|
|
Salvini Andrea |
| No. 303 |
Ageing Management Program revision for the Pavia
TRIGA MK II research reactor
|
|
Sánchez Perea Miguel |
| No. 1101 |
Analysis of the impact of some post-Fukushima improvements in design extension conditions sequences
|
| No. 1108 |
Application of the generic and specific SPAR-CSN probabilistic safety assessment models to several incidents
|
|
Sanchez-Espinoza Victor Hugo |
| No. 402 |
Thermal-Hydraulic Analysis of the 2nd Stage
Hydroaccumulators Impact in MB/LBLOCA Sequences
along with SBO
|
|
Sasagawa Tsuyoshi |
| No. 703 |
Development of an evaluation method for mobile
radioactive contaminants for assessing public
exposure risk in accidental events during
decommissioning of nuclear power station
|
|
Schlegel Fabian |
| No. 408 |
Simulation of Liquid Waves With Flow Reversal in
Stratified Counter-Current Flow With a Hybrid
Multi-Fluid Model
|
|
Scioscioli Federico |
| No. 405 |
Multiphysics Analysis of an in-core Fission
Product Removal System for the Molten Salt Fast
Reactor
|
|
Scott Thomas B. |
| No. 1002 |
Design of an Automated System for Electrolytic
Fusion Fuel Implantation in Metallic Filaments
|
|
Sears Anna |
| No. 608 |
Direct conditioning of molten salt arising from
the thermal treatment of solid organic waste
|
|
Seubert Armin |
| No. 504 |
Implementation and validation of the steady
state SP3 approximation in the GRS FENNECS code
|
|
Shan Jianqiang |
| No. 416 |
Review of application of FFTBM method for code accuracy quantification
|
|
Shimada Taro |
| No. 703 |
Development of an evaluation method for mobile
radioactive contaminants for assessing public
exposure risk in accidental events during
decommissioning of nuclear power station
|
|
Shortall Ruth |
| No. 803 |
Measuring Social Impacts of Nuclear Closure and
Decommissioning
|
|
Sklenka Lubomir |
| No. 304 |
The European Nuclear Experimental Educational
Platform – ENEEP: Overview and Demonstration
Activities
|
|
Skobe Tomaž |
| No. 208 |
Nuclear Technology Courses in Nuclear Training
Centre Ljubljana
|
|
Slapar Borišek Vesna |
| No. 807 |
Background of Values Used for Exclusion,
Exemption and Clearance of Practices and Sources
from Regulatory Control
|
|
Slavič Slavko |
| No. 912 |
Modernization of the Fuel Assembly Register
Software
|
|
Smodiš Borut |
| No. 305 |
New Research Reactor Developments in Slovenia
|
| No. 310 |
Jožef Stefan Institute TRIGA Research Reactor Activities in the
Period from September 2021 – August 2022
|
|
Snoj Luka |
| No. 304 |
The European Nuclear Experimental Educational
Platform – ENEEP: Overview and Demonstration
Activities
|
| No. 305 |
New Research Reactor Developments in Slovenia
|
| No. 310 |
Jožef Stefan Institute TRIGA Research Reactor Activities in the
Period from September 2021 – August 2022
|
| No. 507 |
On the calculation of adjoint neutron flux in typical PWR for
the determination of the neutron flux redistribution factors
|
| No. 509 |
Modelling gamma calorimetry experiment with JSIR2S code
|
| No. 510 |
Burnup measurements using fuel reactivity worth experiments at
the JSI TRIGA Research Reactor
|
| No. 511 |
Maximum required excess reactivity due to Xe-135 “poisoning”
|
| No. 911 |
Simulation of load following operation with a PWR reactor
|
| No. 912 |
Modernization of the Fuel Assembly Register Software
|
| No. 1003 |
Cross-section analysis for neutron producing fusion reactions in
pre-fusion power operation of the ITER tokamak
|
|
Šadek Siniša |
| No. 519 |
Dose Rate Assessment around the PCFV Release
Line during Severe Accident Conditions in
Nuclear Power Plant Krsko
|
| No. 1117 |
Calculation of the QUENCH-02 experiment with the ASYST code
including the uncertainty evaluation
|
| Škarohlíd Jan |
| No. 909 |
Seasonal and daily operation of nuclear based
district heating system with varying energy
demand
|
|
Štancar Žiga |
| No. 1003 |
Cross-section analysis for neutron producing
fusion reactions in pre-fusion power operation
of the ITER tokamak
|
|
Štrubelj Luka |
| No. 410 |
Passive Isolation Condenser Modeling With Apros
Computer Code
|
|
Takeda Seiji |
| No. 703 |
Development of an evaluation method for mobile
radioactive contaminants for assessing public
exposure risk in accidental events during
decommissioning of nuclear power station
|
|
Tarfila Patrik |
| No. 1012 |
Development of a Thermohydraulic Model for DTT
PFU
|
|
Tekavčič Matej |
| No. 408 |
Simulation of Liquid Waves With Flow Reversal in
Stratified Counter-Current Flow With a Hybrid
Multi-Fluid Model
|
| No. 414 |
Application of enhanced phase-change model for simulation of
film boiling around a cylinder
|
| No. 1011 |
Simulation of Natural Convection in DEMO Cryostat During Helium
Ingress Accident
|
|
Tiselj Iztok |
| No. 305 |
New Research Reactor Developments in Slovenia
|
|
Tormási Attila |
| No. 304 |
The European Nuclear Experimental Educational
Platform – ENEEP: Overview and Demonstration
Activities
|
|
Trkov Andrej |
| No. 1003 |
Cross-section analysis for neutron producing
fusion reactions in pre-fusion power operation
of the ITER tokamak
|
|
Umminger Klaus |
| No. 417 |
Review of fonesys and silence nuclear thermal-hydraulic networks achievements
|
|
Uršič Mitja |
| No. 305 |
New Research Reactor Developments in Slovenia
|
| No. 414 |
Application of enhanced phase-change model for simulation of
film boiling around a cylinder
|
| No. 1010 |
Analysis of Large Helium Ingress into the DEMO Cryostat Using
MELCOR for Fusion
|
| No. 1011 |
Simulation of Natural Convection in DEMO Cryostat During Helium
Ingress Accident
|
| No. 1106 |
Analysis of Influence of DEC Equipment on Severe Accident
Development
|
| No. 1115 |
Simulation of fuel-coolant interaction in stratified
configuration in reactor geometry
|
|
Van Bastian Levi |
| No. 613 |
Towards More Ductile Refractory High-Entropy
Alloys at Room Temperature
|
|
Vasileska Ivona |
| No. 1013 |
Kinetic Effects in ITER Scrape-off Layer
|
|
Vécsi Áron |
| No. 401 |
SURET is a new form of subchannel
thermohydraulic calculations
|
|
Vehovar Dragotin |
| No. 913 |
Dynamic Electrical Simulation Model of NPP Krsko
|
|
Verbelen Yannick |
| No. 1002 |
Design of an Automated System for Electrolytic
Fusion Fuel Implantation in Metallic Filaments
|
|
Vilimová Eva |
| No. 1202 |
Special experimental environment for Gen. IV
reactors with graphite reflector
|
| No. 516 |
Neutronic Analysis of Various Fuels for the
TEPLATOR HT
|
|
Villa Mario |
| No. 304 |
The European Nuclear Experimental Educational
Platform – ENEEP: Overview and Demonstration
Activities
|
|
Vivancos Arturo |
| No. 503 |
Burnup code automation and optimization - fuel assembly application
|
|
Vokal Nemec Barbara |
| No. 802 |
Regulatory Requirements for Siting of New
Slovenian NPP
|
|
Vrban Branislav |
| No. 304 |
The European Nuclear Experimental Educational
Platform – ENEEP: Overview and Demonstration
Activities
|
| No. 501 |
The Definition of Mini Labyrinth Benchmark for Radiation
Shielding Calculations
|
| Wallace-Smith Tom |
| No. 1002 |
Design of an Automated System for Electrolytic
Fusion Fuel Implantation in Metallic Filaments
|
| Weisen Henri |
| No. 1000 |
Overview of the JET Deuterium-Tritium fusion
experiments
|
|
Wohleber Xavier |
| No. 305 |
New Research Reactor Developments in Slovenia
|
|
Zajec Boštjan |
| No. 406 |
Experimental study on bubble size distributions
in horizontal narrow-gap annular heat exchanger
|
| No. 413 |
Design optimization of heat transfer performance in the heads of
flow boiling experiment
|
|
Založnik Matija |
| No. 1011 |
Simulation of Natural Convection in DEMO
Cryostat During Helium Ingress Accident
|
|
Závorka Jiří |
| No. 513 |
Moderator Heat Sources in TEPLATOR District
Heating SMR
|
| No. 515 |
Calculation and verification of the new neutron absorbers in a
well-defined core in LR-0 reactor
|
|
Zehetner Milena |
| No. 206 |
Nuclear Education – what influence does online
teaching have – a cause study in Austria
|
|
Zidarič Luka |
| No. 913 |
Dynamic Electrical Simulation Model of NPP Krsko
|
|
Zupančič Kaja |
| No. 905 |
Production of hydrogen and synthetic methane with nuclear power plants
|
|
Žagar Tomaž |
| No. 805 |
Common misconceptions about nuclear energy - case study from interactions in visitors center
|
| No. 905 |
Production of hydrogen and synthetic methane with nuclear power plants
|
|
Žefran Bojan |
| No. 912 |
Modernization of the Fuel Assembly Register
Software
|
|
Železnik Nadja |
| No. 701 |
Deep Borehole Repository of HLW and SF - State
of knowledge by SITEX.Network
|
|
Žerovnik Gašper |
| No. 511 |
Maximum required excess reactivity due to Xe-135
“poisoning”
|
| No. 911 |
Simulation of load following operation with a PWR reactor
|
|
Žiber Ylenia |
| No. 312 |
Testing of Silicon Carbide Neutron Detector for
Detection of Fast Neutrons
|
|
Živko Tomi |
| No. 802 |
Regulatory Requirements for Siting of New
Slovenian NPP
|
|
Žohar Andrej |
| No. 1003 |
Cross-section analysis for neutron producing
fusion reactions in pre-fusion power operation
of the ITER tokamak
|
|
Žvar Matjaž |
| No. 205 |
Excellence in operator fundamentals at NEK
|