Welcome to the

IRIS + RRFM

Conference App!
 

Here you can find all the info regarding the Programmes of RRFM, IRIS and SMaRRt.

All the sessions, all the tracks on this App!

Once downloaded, you can use the app to:

  • View the event agenda

  • Receive last-minute session changes and other important updates from the organisers

  • Book meeting rooms

  • Vote for your favourite Student and Poster presentations

  • Chat and network with your fellow attendees

Programme

International Radioisotope Supply Chain Meeting

09:00 — 11:00

Chair: F. Klaasen, NRG Pallas, The Netherlands

Keynote Speakers

Welcome Address and Introductory Notes
by P. Luijten, NRG Pallas, The Netherlands

Interdependencies and challenges along the radioisotope supply chain
N. Mario,  NucAdvisor, France

From PRISMAP to PRISMAP+: introducing emerging radionuclides for medical applications
U. Koester, ILL, France

Radionuclide production from bench to bedside – the example of Terbium 161
N. van der Meulen, PSI, Switzerland

The challenges of developing a radioisotope supply chain  - Actinium-225
S. Van den Berghe, PanTera, Belgium

Establishing a reliable supply chain for Lutetium 177
N. Quigley, ITM Radiopharma, Germany

11am – 11.30am | Coffee Break

11:30 — 13:00

Chair: R. Eloirdi, JRC
Introductory notes by the Chair

Keynote Speakers

Radionuclides in industrial, agricultural, civil society and environmental applications
T. Bjornstad, University of Oslo; Liv Stravsetra, Institute for Energy Technology, Norway

Radioisotope Use for Space Needs: Developing a European Capability
S. Barron, ESA

Extraction of isotopes from waste – turning by-products into valuable resources
J.F. Valery, ORANO, France

1.00pm – 2.00 pm | Lunch Break

14:00 — 15:40

Chair: S. Van den Berghe, PanTera, Belgium

Keynote Speakers

Advancing Stable Isotope Separation - Technologies and Applications
L. Ashton, Urenco, UK

Building a Reliable Stable Isotopes Supply Chain for Quantum and Healthcare
L. Bigot, ORANO, France

  • Combined Q & A

Presentation

Current and Planned Improvements to Radioisotope Production at Oak Ridge National Laboratory

Bryan, C. (1)

1 - Oak Ridge National Laboratory, United States

3.40 pm - 4.10 pm | Coffee Break

16:10 — 17:50

Chair: B. Stepnik, Framatome, France

Keynote Speaker

Target Preparation, Cross-Section Reactions, and Side Products - Implications for the Supply Chain
F. Haddad, Arronax, France

Presentations

Radiometal production with hybrid targets

Szikra, D. (1)

1 - Syniq Ltd, Hungary

Development of a process for recovering Ra 226 from legacy sources : a matter of sustainability and sovereignty for a European production of Ac225, a very promising radioisotope for cancer treatment

Moreau, C. (1); Feydi, P. (1); Brillon, A. (1); Celier, M. (1); Wagner, C. (1); Morlaes, I. (1); Morel, B. (1)

1 - ORANO, France

Separation and purification of Ag-111 from neutron-irradiated Pd targets

Karantoumanis, F. (1); Rovan Stiplošek, L. (1); Jaćimović, R. (1); Štrok, M. (1)

1 - Jožef Stefan Institute, Slovenia

Neutronic Evaluation of Ir-192 in SAFARI-1 research reactor

Chinaka, E. (1); Bonnanye, G. (1); Tchonang Pokaha, M. (1); Jacobs, C. (1)

1 - The South African Nuclear Energy Corporation (Necsa) SOC Ltd, South Africa

6.30 pm – 9.00 pm | Evening Reception

Joint IRIS-RRFM Walking Dinner

Note: A registration desk for arriving RRFM participants will be open from 5.00 pm

RRFM 2026

21/04/2026, 09:00 — 21/04/2026, 10:30

Chair : S. Van Dyck, SCK-CEN, Belgium                                                                                   

Host Country Presentation: Newbuild in the Netherlands - on the brink of a new nuclear era
G.J.L.M. de Haas, Chairman of the Netherlands Nuclear Society

ERVI: European Radioisotope Valley Initiative to secure the supply of medical radioisotopes in the European Union
G. Simeonov, European Commission

Unlocking the Potential of Radiopharmaceuticals in Europe: Strategic Challenges and Policy Priorities – presentation of the Position Paper of the ENS High Scientific Council
S. Baatout, ENS High Scientific Council

An update from the U.S. Department of Energy's Office of Isotope R&D and Production
C. Landers, DOE  

10.30am – 11am | Coffee Break

21/04/2026, 11:00 — 21/04/2026, 12:40

Chair: K. Dunn, IAEA                                                                                                                      

Preliminary prediction of fuel thermal conductivity evolution in high-density silicide fuels

Ye, B. (1); Puig, F. (1); Mei, Z. (1); Kim, Y. S. (1); Park, G. (1); Shu, S. (1); Licht, J. (1); Wilson, E. (1); Yacout, A. (1); Leenaers, A. (2); Wight, J. (2)

1 - Argonne National Laboratory, United States

2 - SCK CEN, Belgium

STUDY OF ALUMINIUM OXIDATION MECHANISM OF MTR FUEL PLATES IN REACTOR CONDITIONS
 

Valdez Tordoya, D. (1); Haddad Andalaf, R. E. (1)

1 - Comisión Nacional de Energia Atómica, Argentina

3D printing innovative fuel manufacturing – HFIR and DISCOVARY fuel examples

Stepnik, B. (1); Clemencon, J. (1); Rontard, C. (1)

1 - FRAMATOME , France

Present status of regulatory compliance procedure in Japan for the Kindai University Reactor LEU Conversion Project

Hohara, S.-Y. (1); Shiga, H. (1); Sakon, A. (1); Sugiyama, W. (1); Yamada, T. (1); Wakabayashi, G. (1); Tabuchi, M. (1); Sugiura, N. (1); Nishimura, T. (1); Yamanishi, H. (1); Heltemes, T. A. (2); Stevens, J. G. (2); Stratton, C. D. (2); Kalimullah, M. (2); Lell, R. M. (2)

1 - Kindai University, Japan

2 - Argonne National Laboratory, United States

PreP-HALEU: Preparation works for establishing an HALEU production capacity in Europe

Gathmann, R. (1); Stepnik, B. (1); Termeau, L. (1); 1 - Framatome, France

12.40pm – 1.40pm | Lunch Break

21/04/2026, 13:40 — 21/04/2026, 15:00

Chair: J. Marques, Instituto Superior Tecnico, Portugal                                                     

The subcritical reactor VR-2 and its experimental program

Rataj, J. (1); Fejt, F. (1); Hercik, M. (1)

1 - Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, Czech Republic

First year of user-operation with a cold source for the Delft research reactor

Plomp, J. (1)

1 - Delft University of Technology, Netherlands

Experimental measurement of nuclear heating rate using a dual-sample CALORRE calorimeter prototype in the JSI TRIGA reactor

Volte, A. (1); Carette, M. (1); Slaoui, A. (1); Radulovic, V. (2); Snoj, L. (2); Lyoussi, A. (3); Reynard-Carette, C. (1)

1 - Aix Marseille Univ, Université de Toulon, CNRS, IM2NP, Marseille, France, France

2 - Reactor Physics Division, Jožef Stefan Institute, Ljubljana, Slovenia, Slovenia

3 - CEA, DES, IRESNE, DER, France

The Day as a Reactor Physicist at VR-1 reactor for High school students

Novak, O. (1); Frybortova, L. (1); Rataj, J. (1)

1 - Czech Technical University in Prague, Czech Republic

3.00pm – 3.30pm | Coffee Break

21/04/2026, 15:30 — 21/04/2026, 16:30

Chair: S. van Dyck, SCK-CEN, Belgium; E. Proust, ENS High Scientific Council           

Presentation of the ENS HSC PhD Award 2025 Winner:

  • On the Physics of a Core Disruptive Accident in a Heavy Liquid Metal Fast Reactor | Case Study: MYRRHA
    Đ. Petrović, University of Leuven, Belgium

Following the presentation, the ENS High Scientific Council PhD Award will be formally conferred.

Student Competition

VOTE HERE for your favourite work presented during the Student Competition!

Molybdenum disulfides (MoS2) materials for a low-specific activity Mo-99/Tc-99m generator

 Gauri, G. (1); Denkova, A. (1); De Kruijff, R. (1)

1 - Delft University of Technology, Netherlands

Increasing 166Ho Specific Activity through the Szilard-Chalmers Effect in 165Ho-Loaded Zeolites A and Y

Spruit, E. (1); Djanashvili, K. (1); De Kruijff, R. (1)

1 - Applied Radiation and Isotopes, Delft University of Technology, Netherlands

Design and Proof-of-Concept Development of a Precision Measurement System for Fuel Plate Inspection

Sperry, E. (1); Fuentes Rodriguez, D. (2); Maier, A. (3); Lansing, C. (4); Koralewski, A. (5); Mcneff, P. (6); Catalan, M. (6)

1 - University of Washington, United States

2 - Florida International University, United States

3 - The Ohio State University, United States

4 - Washington State University Tri-Cities, United States

5 - Carroll College, United States

6 - National Security Directorate, Pacific Northwest National Laboratory, United States

Thermo-Mechanical Characterisation of a Uranium Alloy for Nuclear Research Reactors

Guyot, B. (1); Touzin, M. (2); Béclin, F. (2); Stepnik, B. (3); Medyk, L. (3)

1 - Framatome / Univ. Lille, UMR 8207 - UMET - Unité Matériaux et Transformations, France

2 - Univ. Lille, UMR 8207 - UMET - Unité Matériaux et Transformations, France

3 - Framatome, France

Implementation of the Cooling Circuits of FissionIST

Lourenço, A. (1); Marques, J. (1)

1 - Centro de Ciências e Tecnologias Nucleares, Instituto Superior Técnico, Portugal

Assessment of Pool Activation in the Portuguese Research Reactor (RPI) for Decommissioning Using Monte Carlo Simulations

Vítor, C. M. (1); Marques, J. G. (1)

1 - Centro de Ciências e Tecnologias Nucleares, Instituto Superior Técnico, Portugal

 

 

Development of a new data processing tool dedicated to the calibration of calorimeter prototypes using a LabVIEW environment

Preite, R. (1); Volte, A. (1); Carette, M. (1); Radulovic, V. (2); Snoj, L. (2); Lyoussi, A. (3); Reynard-Carette, C. (1)

1 - Aix Marseille Univ, Université de Toulon, CNRS, IM2NP, France

2 - Reactor Physics Division, Jožef Stefan Institute, Slovenia

3 - CEA, DES, IRESNE, DER, France

First nuclear heating measurements in stainless steel and tungsten at a fixed axial position in the JSI TRIGA reactor thanks to a dual-sample CALORRE calorimeter

Slaoui, A. (1); Volte, A. (1); Carette, M. (1); Radulovic, V. (2); Snoj, L. (2); Lyoussi, A. (3); Reynard-Carette, C. (1)

1 - Aix Marseille Univ, Université de Toulon, CNRS, IM2NP,  France

2 - Jožef Stefan Institute, Slovenia

3 - CEA, DES, IRESNE, DER, France

Thermally Driven Corrosion and Its Oxide–Acoustic Fingerprints as Diagnostic Indicators of Ageing in TRIGA Research Reactor Tank Liners

Trisnawan, V. (1); Basuki, P. (2); Wafda, H. (3); Himawan, R. (2); Kurniadi, D. (1)

1 - Faculty of Industrial Technology, Bandung Institute of Technology, Indonesia

2 - Directorate of Nuclear Facility Management, National Research and Innovation Agency, Indonesia

3 - Research Organization for Nuclear Energy, National Research and Innovation Agency, Indonesia

4.30pm – 5.10pm | Coffee Break

21/04/2026, 16:30 — 21/04/2026, 17:10

VOTE HERE for your favourite work presented during the Student Competition!

Best Poster Award sponsored by 

On a High-Resolution Neutron Scattering Studies of Substructure of TiAl Polycrystalline Alloys

Mikula, P. (1); Michalcová, A. (2); Ryukhtin, V. (1)

1 - Nuclear Physics Institute CAS, Czech Republic

2 - Dept. of Metals and Corrosion Engineering, Uni. of Chemistry and Technology, Czech Republic

The Educational Impact of Research Reactor Experiences on Students’ Perception of Nuclear: The INSPIR Project

Canziani, L. (1); Grosso, G. (1); Fabiano, M. (1); Gandini, A. (2); Pepe, G. (3); Salvini, A. (2)

1 - Department of Chemistry, University ofPavia, Italy

2 - Laboratorio Energia Nucleare Applicata (L.E.N.A.), University of Pavia, Italy

3 - Fondazione IRCCS Policlinico San Matteo, Pavia, Italy

A Study on Irradiation Test of Innovative Research Reactor Fuel in HANARO and its PIE Results

Park, D. J. (1); Cho, T. W. (1); Jeong, G. Y. (1); Tahk, Y. W. (1); Park, J. M. (1); Kim, H. M. (1); Jeong, Y. J. (1)

1 - Korea Atomic Energy Research Institute, Korea, Republic of

Presentation of PLEIADES/MAIA MTR fuel performance code

Marois, G. (1); Lorenzo, D. (1)

1 - CEA (Commissariat à l'énergie atomique et aux énergies alternatives), France

THE INFLUENCE OF NEUTRON POPULATION SETTINGS IN DEPLETION CALCULATIONS FOR THE ‘HOR’ WITH SERPENT 2

Winkelman, A. (1); Hut, T. (1); Kaaijk, C. (1)

1 - Hoger Onderwijs Reactor, Delft University of Technology, Netherlands

The role of an owner engineer in a new-build research reactor project

Ivanovic, S. (1)

1 - Tractebel, Belgium

Design and Safety Assessment of Irradiation Test for i-SMR Control Rod in HANARO

Park, J. (1); Yang, S. W. (1); Sung Jae, P. (1); Jong Woo, K. (1); Ye Eun, N. (1); Yeonsoo, N. (2); Daewoon, C. (2)

1 - Korea Atomic Energy Research Institute, Korea, Republic of

2 - KEPCO Nuclear Fuel, Korea, Republic of

Plan and Current Status of Thermal-Hydraulic Safety Analysis of the New Research Reactor to be Installed at the Monju Site in Japan

Nagatake, T. (1); Tsumura, T. (1); Izawa, K. (1); Arai, M. (1)

1 - Japan Atomic Energy Agency, Japan

Ageing Management applied from design stage

Cocco, R. (1); Rossi, G. (1); Petriw, S. (1)

1 - INVAP S.A.U., Argentina

Budapest Neutron Centre

Dudás, Z. (1); Baranyai, R. (1); Fehér, Á. (1); Gméling, K. (1); Kasztovszky, Z. (1); Len, A. (1); Markó, M. (1); Maróti, B. (1)

1 - Budapest Neutron Centre, Institute for Energy Security and Environmental Safety, HUN-REN Centre for Energy Research, Hungary

Irradiation optimisation of Ir-192 sealed sources in the MARIA research reactor, with particular focus on obtaining low-activity sources.

Prokopowicz, R. (1); Konior, M. (2); Kuczkowska, A. (2); Biała, E. (2); Cybowska, J. (1); Madejowski, G. (1); Ziemba, M. (1)

1 - The MARIA Reactor Operations Department, NCBJ,  Poland

2 - Production Department, NCBJ OR Polatom, Poland

Supporting countries implementing their Research Reactor program - Feedback from four projects, three vendors over the past decade

Girard, J. P. (1); Vallée, A. (1); Buisson, M. (1)

1 - NucAdvisor, France

Localization of Peak Fuel Temperatures in the Multi-Layer Tubular Fuel Assemblies of the Budapest Research Reactor

Sebó, P. L. (1)

1 - HUN-REN EK, Hungary

FROM NEUTRONS TO THERAPY: CONCEPTUAL DESIGN FOR THE PRODUCTION OF NCA 177LU AT THE MARIA RESEARCH REACTOR

Konior, M. (1); Biała, E. (1); Kuczkowska, A. (1)

1 - Production Department, NCBJ OR Polatom, Poland

Advances in STAT7 v2.0 – Steady-State Thermal Hydraulics Software for Research Reactors With Uncertainty Propagation Using Monte Carlo

Wilson, G. (1); Yang, S. (1); Yoon, D. (1); Wang, G. (1); Hu, L.-W. (2); Thomas, J. (1); Wilson, E. (1)

1 - Argonne National Laboratory, United States

2 - Massachusetts Institute of Technology, United States

Advances in PLTEMP/ANL Code and Application for Design and Safety Analysis of Research Reactors

Kalimullah, M. (1); Son, H. M. (1); Olson, A. (1); Feldman, E. (1); Thomas, J. (1); Licht, J. (1)

1 - Argonne National Laboratory, United States

Structural Analysis of HFIR HEU Plate in Reactor Conditions

Ross, M. (1); Shehu, K. (2); Sitek, M. (3)

1 - Oak Ridge National Laboratory, United States

2 - Technical University of Munich, Germany

3 - Argonne National Laboratory, United States

Irradiation Behavior of High-density Atomized U3Si2 Fuel Assembly in BR2
 

Cho, T. W. (1); Jeong, Y. J. (1); Park, D. J. (1); Park, J. M. (1); Wight, J. (2); Acevedo, B. (2); Ann, L. (2)

1 - Korea Atomic Energy Research Institute (KAERI), Korea, Republic of

2 - Belgian Nuclear Research Centre (SCK CEN), Belgium

Long-term tests on metal seals in the compressed state and numerical simulation of thermomechanical behaviour

Sagradov, I. (1); Jaunich, M. (1); Kandemir, T. (2); Drobniewski, C. (2); Wolff, D. (1)

1 - Bundesanstalt für Materialforschung und -prüfung (BAM), Germany

2 - Bundesamt für die Sicherheit der nuklearen Entsorgung (BASE), Germany

Technical Challenges of Periodic Safety Review for the Kyiv Research Nuclear Reactor

Meleshko, H. (1); Mazurok, O. (1); Stratilat, D. (2); Zuyok, V. (3); Lavrenov, D. (4)

1 - Energy Safety Group LLC (ES Group LLC), Ukraine

2 - Institute for Nuclear Research of National Academy of Sciences of Ukraine, Ukraine

3 - National Science Centre “Kharkov Institute of Physics and Technology”, Ukraine

  4 - “Public organization “Ukrainian Nuclear Society”,   Ukraine

21/04/2026, 17:10 — 21/04/2026, 18:30

Chair: F.R. Bellino, INVAP, Argentina       

DETERMINISTIC SAFETY METHODOLOGY FOR THE PALLAS-REACTOR

Franssen, S. (1); Vega, C. (1)

1 - NRG PALLAS, Netherlands

Research Rigs design for the PALLAS reactor

Knol, S. (1); Boomstra, D. (1); Beck, R. (1); Grismanovs, V. (1)

1 - NRG PALLAS, Netherlands

Modelling the consequences of atmospheric radiological releases from the PALLAS reactor

Van Oudenaren, G. (1); Soubourou, P. (1)

1 - NRG PALLAS, Netherlands

PVISOR - A PYTHON LIBRARY FOR PROCESSING NUCLEAR SAFETY CODE OUTPUT

Franssen, S. (1); Verdonschot, B. (1); Breijder, P. (1)

1 - NRG PALLAS, Netherlands

International Radioisotope Supply Chain Meeting

21/04/2026, 11:00 — 21/04/2026, 12:40

Chair : S. Van Dyck, SCK-CEN, Belgium                        

Keynote Speaker                                                                         

Particle Accelerator for Radioisotope Production - Building Global Supply Chains for a Growing Demand
J.M. Geets, IBA, Belgium

Presentations

Simulation of Concrete Activation by a Cyclotron Source and the Economic Impact on Waste Disposal

Storms, J. (1); Vangansbeke, E. (1)

1 - Tractebel Engineering S.A., Belgium

Design of Research Reactors and Radioisotope Processing Facilities from a Radioisotope Supply Chain Perspective

Menbribe, M. E. (1); Cruz, M. L. (1); Wilkinson, M. V. (1)

1 - INVAP, Argentina

Moderator Assembly Design for Multi-isotope Production using high-yield D-T Neutron Generator

Saxena, A. (1); Swami, H. L. (1); Abhangi, M. (1); Vashi, V. (1); Vala, S. (1); Kumar, R. (1)

1 - Institute for Plasma Research, India

Establishing a Reactor-Based Radioisotope Program in Korea: Opportunities with the New Research Reactor

Lee, S.-K. (1)

1 - KAERI, Korea, Republic of

12.40pm – 1.40pm | Lunch Break

21/04/2026, 13:40 — 21/04/2026, 15:00

Chair : N. van der Meulen, PSI, Switzerland    

Keynote Speaker                                                                         

Enabling Efficient Radioisotope Production and Supply – Field Lab
M. Bogert, NRGPallas, The Netherlands

Presentations

Parcoval project: Pd recovery from Spent Nuclear Fuels

Berenguer-Besnard, P. (1); Ropp, A. (2); Bahri, M. (3); Rougeaux, I. (4)

1 - Orano Recyclage, France

2 - Orano Support DRD, France

3 - Orano Recyclage, France

  4 - CEA LITEN, France

Downstream Pb-212 purification for radiolabeling of Targeted Alpha Therapy (TAT) compounds

Marshall, S. (1); Villas Boas, C. (1); Henk, T. (1); Bushman, G. (1); Schmitz, J. (1); Verma, S. (1)

1 - TAG1, United States

3.00pm – 3.30pm | Coffee Break

21/04/2026, 15:30 — 21/04/2026, 16:30

Chair: R. Baranczyk, Euratom Supply Agency                     

Keynote Speakers                                                 

The Scientific Background
H. Mansoux, B. Louis, IAEA

An Industry View
R.W. Brown, Nuclear Medicine Europe  (NMEU)

Combined Q & A and Discussion

4.30pm – 5.10pm | Coffee Break

21/04/2026, 16:30 — 21/04/2026, 17:10

IRIS

On Proton irradiation and transmutation implementation on PyNE-Python library.

Natali, G. (1); Velazquez, D. (2); Plata, C. (2); Pille, G. (1)

1 - Apollo Generators, France

2 - Salomea Solutions, United States

21/04/2026, 17:10 — 21/04/2026, 18:30

Chair : S. Barithel, ORANO, France                  

Keynote Speaker                                                                        

Connecting the Dots - Transportation as the Backbone of the Radioisotope Supply Chain
H. Van De Maele, PHSE International, Belgium

Presentations

Challenges and Opportunities for Automation and Data Analytics in the Radioisotope Supply Chain.

Alcala, C. L. (1); Massera, J. R. (1)

1 - INVAP, Argentina

COMPARATIVE EVALUATION OF DEPLETED URANIUM CASKS FOR THE TRANSPORT OF LUTETIUM-177

Jacobs, C. (1); Bedhesi, L. (1); Chinaka, E. (1); Setlhare, A. (2)

1 - South African Nuclear Energy Corporation (Necsa), South Africa

2 - North West University, Potchefstroom Campus, South Africa

Optimal Production Scheduling and Distribution of a Medical Radioisotope Under Uncertainty

Nguyen, T. (1); Arts, J. (2); Seranillla, B. K. (2)

1 - SCK CEN, Belgium

  2 – University of Luxembourg, Luxembourg

SMR-AMR and R&D: Innovating Together

09:00 — 11:00

Chair: S. Monti, European Nuclear Society                                                                           

European Commission SMR IA: Present Status and Key Issues
B. Salha, SNETP

Critical Challenges for Innovative Reactor Technologies
F. Reitsma, IAEA

Rolls-Royce – Towards reactor licensing: progress and challenges
S. McFarlane Smith, Rolls-Royce

Advancing U.S. Reactor Demonstrations: An Overview of the 2025–2026 Pilot Program
N.N. , DOE (tbc)

11.00am – 11.30am | Coffee Break

11:30 — 13:00

Chair: D. Wells, EPRI, US                                                                              

Overview of developments for advanced fuel, with a specific focus on HTR project development
B. Stepnik, Framatome

Progress and timeline for Molten salt fuel manufacturing and reprocessing
E. Capelli, ORANO

Thorizon’s developments related to fuel development
S. de Groot, Thorizon

Eagle 300: recent advances in fuel development
M. Caramello, Ansaldo

Each presenter will give a presentation of 15 minutes, followed by a Panel Discussion with all presenters.

1pm – 2pm | Lunch

14:00 — 15:20

Chair: F. Rocchi, ENEA, Italy                                                                                              

Industrializing sodium-cooled fast reactors for a carbon-free future
C. Bisor, HEXANA, France

Licensing of a novel nuclear test facility for the safe testing of new reactor concepts - A project by Copenhagen Atomics and PSI
M. Streit, PSI, Switzerland

LEANDREA - Advancing the design for timely realization
M. Greco, SCK-CEN, Belgium

Advances in Lead Cooled Reactor Safety, Materials, and Instrumentation
F. Garcia Ferrè, Newcleo

3.20pm – 3.50pm | Coffee Break

15:50 — 17:30

Chair: R. Garbil, European Commission, DG RTD                         

Advancing MSR Technology: The Copenhagen Atomics-PSI Molten Salt Experiment - Progress Since RRFM 2025

Frajtag, P. (1); Streit, M. (1); Stubsgaard, A. (2); Swalwell, G. (2); Chierici, L. (2); Pautz, A. (1)

1 - Paul Scherrer Institut, Switzerland

2 - Copenhagen Atomics A/S, Denmark

HITEC – In-pile Creep evaluation for materials of advanced reactors

Laot, M. (1); Hania, R. (1); Naziris, K. (1); Fedorov, S. (1); Elenbaas, J. (1); Rossouw, D. (1); Kronenberg, T. (1)

1 - NRG PALLAS, Netherlands

Fuel Irradiation Testing Capabilities at BR2 for Small Modular Reactors

Boer, B. (1); Bosch, R.-W. (1); Bonny, G. (1); Verwerft, M. (1)

1 - SCK CEN (Belgian Nuclear Research Centre), Belgium

Impact of Corrosion and Estimation of Effective Corrosion Depth in 15-15Ti Cladding Tubes Using the Small Punch Test Technique

Holmstrom, S. (1); Simonovski, I. (2); Nindiyasari, F. (3)

1 - SCKCEN, Belgium

2 - JRC, Joint Research Centre, Netherlands

  3 - NRG PALLAS, Netherlands

Analysis and preparation of the methodology for assessing the placement of small and medium reactors in the Czech Republic conditions

Novak, O. (1); Kozic, J. (1); Frantova, M. (1); Stemberk, P. (1); Rastislav, M. (1); Zemanova, A. (1); Vojackova, J. (2); Hroch, T. (3); Jelínek, J. (3)

1 - Czech Technical University in Prague, Czech Republic

2 - Brno University of Technology, Czech Republic

  3 - Czech Geological Survey, Czech Republic

15:50 — 17:50

 

SMaRRt - Poster

Irradiation Performance of Ni-base Structural Alloys for Applications in Molten Salt Nuclear Reactors

Naziris, K. (1); Marques Pereira, V. (1); Hania, R. (1); Rossouw, D. (1)

1 - NRG PALLAS, Netherlands

Pre-Feasibility Study of Uranium Silicide-Aluminium Dispersion Fuel as an Alternative Fuel in WWR-K Research Reactor

Sairanbayev, D. (1); Shaimerdenov, A. (1); Gizatulin, S. (1)

1 - Institute of Nuclear Physics, Kazakhstan

Small Modular Reactors for Hydrogen Production: Technologies, Advantages, and Barriers

Bartali, R. (1); Testi, M. (1); Debona, E. (1); Bolognese, M. (1); Crema, L. (1)

1 - Fondazione Bruno Kessler, Sustainable Energy, Italy

Pioneering the future of nuclear alloys: Lab casting (VIM), hot and cold rolling, annealing & characterisation

Puype, A. (1); Keyzer, S. (1); De Wispelaere, N. (1); Maas, F. (1)

1 - OCAS NV, Belgium

From Reactor Concept to Back-end Readiness: Mapping R&D Needs for SMR/AMR Deployment from the Back-end Perspective
 

Martinez, J. S. (1); García, D. (1); Canals, I. (1); Wasselin, V. (2); Tribet, M. (3); Galán, H. (4); Rodríguez-Villagra, N. (4); Álvarez, F. (4); Sánchez-García, I. (4); Milena, A. (4); Nachmilner, L. (5); Houghton, R. (6); Herdzik-Koniecko, I. (7); Narkunas, E. (8); Cairns, M. (9); Clark, K. (9); Magugliani, G. (10); Bucur, C. (11); Fache, M. (12); Weetjens, E. (12); Hanusova, I. (13); Tkaczyk, A. (14); Naumer, S. (15); Keto, P. (15); Schatz, T. (15)

1 - Amphos 21, Spain

2 - Agence Nationale pour la Gestion des Déchets Radioactifs (Andra), France

3 - CEA, ISEC, France

4 - Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (CIEMAT), Spain

5 - Centrum výzkumu Řež s.r.o, Czech republic

6 - Galson Sciences Ltd, United kingdom

7 - Institute of Nuclear Chemistry and Technology (INCT), Poland

8 - Lithuanian Energy Institute, Lithuania

9 - Nuclear Waste Services, United kingdom

10 - Politecnico di Milano, Italy

11 - Institute for Nuclear Research Pitesti (RATEN ICN), Romania

12 - SCK CEN, Belgium

13 - SÚRO, Czech republic

14 - University of Tartu, Estonia

15 - VTT Technical Research Centre of Finland Ltd, Finland

7.30pm – 0.00am | Conference Dinner

RRFM 2026

1:00pm – 2.00pm | Lunch Break

21/04/2026, 14:00 — 21/04/2026, 15:20

Chair: I. Vidovszky, HUN-REN-CER, Hungary                                                                         

FIR 1 RESEARCH REACTOR DECOMMISSIONING: FINAL DISPOSAL OF THE WASTE

Kaisanlahti, M. (1); Oinonen, V. (1)

1 - Fortum Power and Heat Oy, Finland

FIR 1 RESEARCH REACTOR DECOMMISSIONING LESSONS LEARNED

Oinonen, V. (1)

1 - Fortum, Finland

 

Low-Level Waste Classification with Convolutional Neural Networks

Li, T. (1); Li, Z. (1)

1 - Department of Civil Engineering, McMaster University, Canada

21/04/2026, 14:00 — 21/04/2026, 15:20

Chair: C. Rontard, Framatome, France                                                                                                 

Asset Management features for a Research Reactor

Petriw, S. (1); Rossi, G. (1); Roxana, C. (1)

1 - INVAP S.A.U., Argentina

Investigation of Irradiated Aluminium Alloys for Research Reactors: Insights from the first year of the Horizon Europe MAGIC-RR Project

Kolluri, M. (1); Naziris, F. (1); Francois, P. (2); Szenthe, I. (3); Dommelen, J. A. W. V. (4); Gonzalez-Garcia, Y. (5); Radiguet, B. (6); Bagot, P. (7); London, A. (8); Namburi, H. (9);  Mostert, J. (10)

1 - NRG PALLAS, Netherlands

2 - CEA, France

3 - HUN-REN-CER, Hungary

4 - Eindhoven University of Technology, Netherlands

5 - TU Delft, Netherlands

6 - University of Rouen, France

7 - University of Oxford, United Kingdom

8 - UKAEA, United Kingdom

9 - CNL, Canada

10 - NECSA, South Africa

ILL’S BRIGHT FUTURE

Estrade, J. (1)

1 - INSTITUT LAUE LANGEVIN, France

HFR Beryllium Management Program

Van Loggerenberg, P. (1); Silva Pinto Wahnon, S. (1); Davis, L. (1)

1 - NRG PALLAS, Netherlands

3.20pm – 3.50pm | Coffee Break

21/04/2026, 15:50 — 21/04/2026, 17:30

Chair: A. Pichlmaier, TUM, Germany                                                                                         

SAFARI-1 PSR and SALTO Approach to justify Long Term Operation beyond 65 years

Malaka, S. (1)

1 - Necsa-SAFARI-1 , South Africa

FRM II RELAP5 MODEL DEVELOPMENT

Ozar, B. (1); Puig, F. (1); Licht, J. (1); Bergeron, A. (1); Reiter, C. (2); Shehu, K. (2); Bonete-Wiese, D. (2); Schonecker, R. (2); Schlitt , T. (2); Mercz, J. (2)

1 - Argonne National Laboratory, United States

2 - Forschungs-Neutronenquelle Heinz Maier-Leibnitz (FRM II), Technische Universitat Munchen, Germany

FLUIDIC VORTEX DIODES: THE DESIGN TO SAFETY ASSESSMENT 

Bellino, F. (1); Petrini, T. (1); Lazarte, A. (1); Doval, A. (1); Carlevaris, R. (1); Franzé, B. (1)

1 - INVAP, Argentina

Periodic Safety Review of HANARO Research Reactor

Doo, S. (1); Hong, S. (1); Shin, J. (1)

1 - Korea Atomic Energy Research Institute, Korea, Republic of

HOT or NOT: Decay Heat Assessment in MARIA Reactor - Computer Simulations Versus Experimental Measurements

Cybowska, J. (1); Machtyl, T. (1); Marcinkowska, Z. (1); Warszakowski, A. (2)

1 - National Centre for Nuclear Research, Poland

2 - Gdańsk University of Technology, Poland

21/04/2026, 15:50 — 21/04/2026, 17:30

Chair: M. Migdal, NCBJ, Poland                                                       

Validation of MCNP6 and FISPACT-II calculations to predict the activation of selected beta emitters produced in the Budapest Research Reactor

Maróti, B. (1); Kis, Z. (1); Buczkó, N. A. (1); Buczkó, N. A. (2); Gméling, K. (1); Szentmiklósi, L. (1)

1 - Budapest Neutron Centre, Institute for Energy Security and Environmental Safety, HUN-REN Centre for Energy Research, Hungary

2 - Hevesy György PhD School of Chemistry, ELTE Eötvös Loránd University, Hungary

Analysis of the Neutronic and Thermal–Hydraulic Characteristics of Radioisotope Irradiation Targets in High-Flux Research Reactors

Boyi, Y. (1); Lei, S. (1); Jian, L. (1)

1 - Institute of Nuclear and New Energy Technology, Tsinghua University, China

The Role of Low-Power Reactors in Radionuclide Production: Advancements and Educational Impact at LENA

Canziani, L. (1); Grosso, G. (2); Gandini, A. (2); Alloni, D. (2); Pepe, G. (1); Salvini, A. (2)

1 - Fondazione IRCCS Policlinico San Matteo, Pavia, Italy

2 - Laboratorio Energia Nucleare Applicata (L.E.N.A.), University of Pavia, Italy

NEUTRONIC OPTIMIZATION OF MEDICAL RADIOISOTOPES PRODUCTION IN MULTIPURPOSE RESEACH REACTOR

Sarabia, H. G. (1); Bastidas, A. (2); Cruz, M. L. (1); Hergenreder, D. (1)

1 - INVAP SAU, Argentina

2 - INSTITUTO BALSEIRO, Argentina

7.30pm – 0.00am | Conference Dinner

RRFM 2026

22/04/2026, 09:00 — 22/04/2026, 10:40

Chair: B. Stepnik, Framatome, France                                                                                  

IAEA Support for Research Reactor Fuel Cycle Programmes – Achieving Safe, Secure, and Sustainable Fuel Cycle Solutions

Dunn, K. (1); Chakrov, P. (1); Martin, J.-F. (1)

1 - International Atomic Energy Agency, Austria

New Experiment Device for Full-Size Research Reactor Fuel Configurations for irradiation in BR2 under Tailored Thermal Hydraulic and Neutronic Conditions

Rossaert, B. (1); Wight, J. (1); Capriotti, L. (1)

1 - SCK CEN, Belgium

Neutron performance of U-Mo fuel using isotopically modified molybdenum

Blanchet, D. (1)

1 - CEA Cadarache, DES/IRESNE/DER, France

Safety assessment overview for BR2 LEU conversion

Wols, F. (1); Wight, J. (1); Van den Branden, G. (1); Van Dyck, S. (1)

1 - SCK CEN, Belgium

FUTURE-MONO 1 U-10Mo monolithic fresh fuel characterization

Medyk, L. (1); Monier, L. (1); Buniazet, Z. (1); Stepnik, B. (1); Rontard, C. (1); Rodriguez Doring, A. (1); Gathmann, R. (1); Wight, J. (2); Holmström, S. (2); Baumeister, B. (3); Reiter, C. (3); Petry, W. (3); Calzavara, Y. (4); Rodier, M. (5); Federici, E. (5)

1 - Framatome, France

2 - Nuclear Material Science Institute, SCK-CEN, Belgium

3 - Forschungs-Neutronenquelle Heinz Maier-Leibnitz (FRM II)  Technische Universität München, Germany

4 - Institut Laue-Langevin (ILL), France

5 - CEA, DEN, DEC, France

22/04/2026, 09:00 — 22/04/2026, 10:40

Chair: M. Streit, PSI, Switzerland                                                                    

Functional Tests on Reactor Systems as the “Avant-Première” of Commissioning in Research Reactors

Masriera, N. (1); Doval, A. (1); Drexler, J. (1)

1 - INVAP S.A.U., Argentina

Research on Thermodynamic Characteristics in Flow Blockage Accidents of Tsinghua High-Flux Reactor

Zhang, J. (1); Xie, H. (1); Shi, L. (1)

1 - Institute of Nuclear and New Energy Technology, Tsinghua University, China

Cybersecurity and Functional Safety in Research Reactor I&C Systems and Functional Safety in Research Reactor I&C Systems

Edeh, N. (1); Waedt, K. (1)

1 - Framatome GmbH, Germany

APPROACH FOR A UNIFIED LIST OF INITIATING EVENTS FOR RR

Du, Z. (1); Kowalik, M. (1); Mateos Canals, I. (1); Parente, G. (1); Steinrötter, T. (1); Wenke, R. (1)

1 - GRS gGmbH, Germany

Development of Spent Fuel Silo Storage at the Baikal Research Reactor Complex in Kazakhstan

Gaines, K. (1); Bolshinsky, I. (2); Batyrbekov, E. (3); Baklanov, V. (3); Gnyrya, V. (3); Korovikov, A. (3)

1 - Oak Ridge National Laboratory, United States

2 - Idaho National Laboratory, United States

3 - National Nuclear Center of the Kazakhstan, Agency of  the Republic of Kazakhstan for Atomic Energy, Kazakhstan

10.40am – 11.10am | Coffee Break

22/04/2026, 11:00 — 22/04/2026, 12:40

Chair: L. Jamison, ANL, US                                                                                                           

Design studies of the IGR reactor conversion

Irkimbekov, R. (1); Surayev, A. (1); Zhanbolatov, O. (1); Gnyrya, V. (1)

1 - Branch Institute of Atomic Energy RSE NNC RK, Kazakhstan

Advancing LEU Fuel Systems for High-Power Research Reactor Conversion: Insights from the EU-QUALIFY Project

Holmstrom, S. (1); Hernandez Solis, A. (1); Newman, G. (1); Parthoens, Y. (1), Leenaers, A. (1); Capriotti, L. (1); Rossaert, B. (1); Shehu, K. (2);  Reiter, C. (2); Rodrigez Doring, A. (3); Rontard, C. (3); Federici, E. (4); Rodier, M. (4), Frery, F. (5)

1 - SCKCEN, Belgium 

 

2  - Technische Universität München, Lichtenbergstr. 1, 85747 Garching, Germany

3 - Framatome – CERCA, 54, avenue de la Déportation, 26100 Romans-sur-Isère, France

4 - CEA Cadarache, 13108 Saint-Paul-lez-Durance, France

5 - Institut Laue-Langevin (ILL), 71 avenue des Martyrs, CS 20156, 38042 Grenoble, France

UMo monolithic fuel plates manufacturing for TUM reactor conversion

Monier, L. (1); Lemetais, M. (1); Medyk, L. (1); Allenou, J. (1); Reiter, C. (2); Schwarz, C. (3); Lomp, N. (2); Shehu, K. (2); Shi, J. (2); Baumeister, B. (3); Merle, J. (1); Grasse, M. (1); Dardinier, J. (1); Teppe, A.-L. (1); Stepnik, B. (1)

1 - Framatome CERCA, France

2 - Chair of Applied Nuclear Technologies, School of Engineering and Desing, Technische Universität München, Germany

3 - Forschungs-Neutronenquelle Heinz Maier-Leibnitz (FRM II), Technische Universität München, Germany

Structural Design and Analysis of the MITR-III for HALEU Conversion

Foxen, M. (1)

1 - Massachusetts Institute of Technology, United States

Operational Experience in a Wet Storage Facility for Research Reactor Spent Nuclear Fuel

Ferrero, V. C. (1); Flores, M. G. (1)

1 - CNEA, Argentina

22/04/2026, 11:00 — 22/04/2026, 12:40

Chair: S. Knol, NRG PALLAS, Netherlands                                            

Expanding Neutron Beam Capabilities at Low- and Medium-Flux Neutron Sources

Semkova, V. (1); Vargas, E. (1); Ridikas, D. (1)

1 - International Atomic Energy Agency, Austria

Research Reactor Outreach Program - A Collaboration between the  International Atomic Energy Agency and the University of Texas

Landsberger, S. (1); Charlton, W. (1); Egozi, T. (2); Vargas, E. (3); Khalaileh, L. (4)

1 - University of Texas at Austin, United States

2 - Educational Consultant, United States

3 - International Atomic Energy Agency, Austria

4 - Jordan Atomic Energy Commission, Jordan

 

 

The effect of high-temperature neutron irradiation on the corrosion resistance of beryllium and chromium beryllide

Shaimerdenov, A. (1); Kulsartov, T. (2); Askerbekov, S. (1); Akhanov, A. (1); Aitkulov, M. (1); Sairanbayev, D. (1); Podoinikov, M. (3)

1 - The Institute of Nuclear Physics, Kazakhstan

2 - Satpayev University, Kazakhstan

3 - Ulba metallurgical plant, Kazakhstan

Experience in Minimization of Sample Heating During Neutron Irradiation in the Research Reactor

Prokopowicz, R. (1); Madejowski, G. (1); Bąk, Ł. (1); Murawski, Ł. (1); Tuszyński, R. (1); Ziemba, M. (1); Wojtania, G. (1); Wielgosz, M. (1); Furnańczyk, D. (1); Gryc, A. (1); Knake, N. (1); Lechniak, J. (1)

1 - National Centre for Nuclear Research, Poland

12:40pm – 1.40pm | Lunch Break

22/04/2026, 13:40 — 22/04/2026, 15:00

Chair: L.-W. Hu, Massachusetts Institute of Technology, United States                            

New Research Reactor Program at the “Monju” Site, Japan

Sasa, T. (1)

1 - Japan Atomic Energy Agency, Japan

Experimental validation studies for the Kijang Research Reactor

Kim, S. H. (1); Park, K.-J. (1)

1 - Korea Atomic Energy Research Institute, Korea, Republic of

Key considerations in project scoping and procurement strategy for new build research reactors aimed at isotope production and nuclear technology research

Narasimhamurthy, D. (1)

1 - Tractebel Engineering B.V., Netherlands

Status Report on New South Africa’s Multipurpose Reactor Project

Mukwevho, M. (1); Mozagba, A.-T. (1)

1 - The South African Nuclear Energy Corporation, South Africa

22/04/2026, 13:40 — 22/04/2026, 15:00

Chair: A. Leenaers, SCK-CEN, Belgium

Design and Characterization of an Enriched Molten Salt Fuel Capsule Irradiation Experiment

Downey, C. (1); Karlsson, T. (1); Abou-Jaoude, A. (1); Kropp, M. (1); Wamann, S. (1)

1 - Idaho National Laboratory, United States

Conceptual Design of Fuel Testing Oriented Irradiation Loop for MARIA Reactor

Prokopowicz, R. (1); Migdal, M. (1)

1 - National Centre for Nuclear Research, Poland

Comparison of MCNP and Serpent calculations of radiation heatings

Belko, B. (1); Pinta, J. (1)

1 - Research Centre Řež, Czech Republic

 

22/04/2026, 13:40 — 22/04/2026, 14:40

Chair: L. Chabert, TechnicAtome, France                                                             

Neutronic Analysis of MTR Fuel with Cd Burnable Poisons Using MCNP and TRITON Codes

Kim, K.-O. (1); Yoo, H. J. (1)

1 - Korea Atomic Energy Research Institute, Korea, Republic of

VALIDATION OF THE MONTE-CARLO CODE SERPENT 2 FOR CORE FOLLOW AND DESIGN OF THE ‘HOR’

Hut, T. (1); Winkelman, A. (1); Kaaijk, C. (1)

1 - Hoger Onderwijs Reactor, Delft University of Technology, Netherlands

Impact of Burnup-Driven Isotopic Uncertainties on Power Density and Gamma Heating Distributions in Fuel and Structural Materials of a High-Flux Research Reactor

Alhassan, E. (1); Hernandez-Solis , A. (1); Newman, G. (1); Sikik , E. (1)

1 - Belgian Nuclear Research Centre, Belgium

 

3.00pm – 3.30pm | Coffee Break

22/04/2026, 15:30 — 22/04/2026, 16:30

Chair: J. Estrade, ILL, France                                                                           

The concept of new Impulse Graphite Reactor

Zhanbolatov, O. (1); Irkimbekov, R. (1); Surayev, A. (1)

1 - Branch Institute of Atomic Energy RSE NNC RK, Kazakhstan

NA² - A COLLABORATIVE NORDIC APPROACH TO ESTABLISHING A NEW RESEARCH REACTOR: MOTIVATION AND STATUS 2026

Bergdahl, A. (1); Olsson, P. (2); Jakelius, S. (1); Wiese, T. (1)

1 - Nordics Association for Nuclear Acceleration AB, Sweden

2 - KTH Stockholm, Sweden

Multi-Objective Optimization of a new MIT Research Reactor Core Design using a Non-dominated Sorting Genetic Algorithm

Hauptman, S. (1); Buongiorno, J. (1); Craft, A. (2); Hu, L.-W. (1); Kohse, G. (1); Snead, L. (1); Shirvan, K. (1); Forget, B. (1); Crawford, D. (2)

1 - Massachusetts Institute of Technology, United States

2 - Idaho National Laboratory, United States

22/04/2026, 15:30 — 22/04/2026, 16:30

Chair: C. Kaaijk, TU Delft, The Netherlands                                               

Manufacturing of spare control rods for the Hoger Onderwijs Reactor

Tjeertes, D. (1); Van Wijk, N. (1); Kaaijk, C. (1)

1 - Hoger Onderwijs Reactor, Delft University of Technology, Netherlands

 

 

Preliminary Performance Assessment of the Innovative Control Fuel Assembly for the LVR-15 Reactor

Romanello, V. (1); Dambrosio, A. (1); Hrehor, M. (2); Huet, F. (3); Boyard, M. (3)

1 - CVR - Research Centre Rez Nuclear safety department , Czech Republic

2 - SURO - Nuclear safety department - National Radiation Protection Institute, Czech Republic

3 - TechnicAtome, France

Demonstrating SCK CEN’s Full Fuel Qualification Capability with HD USi for BR2

Leenaers, A. (1); Holmström, S. (1); Wight, J. (1); Capriotti, L. (1)

1 - Nuclear Engineering Technology Institute, SCK CEN, Belgium

22/04/2026, 15:30 — 22/04/2026, 16:30

Chair: E. Alhassan, SCK-CEN, Belgium                                                

MIT REACTOR SIMULATOR DIGITAL TWIN DEVELOPMENT AND DEMONSTRATION

Hu, L.-W. (1)

1 - Massachusetts Institute of Technology, United States

MODELLING OF SELECTED VALIDATION EXPERIMENTS IN SUPPORT OF SAFARI-1 SAFETY ANALYSIS

Prinsloo, R. (1); Khoza, S. (1); Martinez-Quiroga, V. (2); Vlok, W. (1); Groenewald, S. (1)

1 - Necsa, South Africa

2 - Energy Software Ltd, Spain

TRAD_SN: Development of an SN Interface to Generate a Problem-Dependent Adjoint Source for Accelerating Monte Carlo Radiation Transport Calculations

Meier, H. (1); Cuello, E. (1); Gray, B. (1)

1 - INVAP S.A.U., Argentina

4.30pm – 5.00am | Closing Session

Technical Tours

RRFM Technical Tours

  • Technical Tour I – NRG PALLAS site in Petten

  • Technical Tour II – URENCO enrichment facility in Almelo

  • Technical Tour III – TU Delft Reactor Institute

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20–24 April 2026
Hilton Garden Inn Leiden, Willem Einthovenstraat, Oegstgeest, Netherlands
Willem Einthovenstraat 3, 2342 BH Oegstgeest ZH, Netherlands