Description
Geometry, radiation transport, activation, multiphysics tools.
Uncertainty quantification.
Variance reduction for MC.
Nuclear data development and experiments
Benchmarking and V&V
AI and ML use for neutronics
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Georg Schnabel (IAEA)09/06/2026, 12:30Nuclear data development and experiments
The Fusion Evaluated Nuclear Data Library (FENDL) has been serving the Fusion Neutronics community for more than three decades, particularly addressing the nuclear data needs of the ITER project, for which it is the design library since FENDL 2.1, released in 2006.
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Its development is driven by an international committee and coordinated by a series of meetings under the auspices of the IAEA... -
Enrique Miralles-Dolz (Princeton Plasma Physics Laboratory)09/06/2026, 14:00Nuclear data development and experimentsOral
Recent community discussions, including WANDA 2024, have highlighted the need for sensitivity studies to prioritize nuclear data improvement efforts for Fusion Energy Sciences. Yet nuclear data sensitivity analyses in fusion are still commonly performed one response at a time, such as tritium breeding ratio or activation, and one component at a time, such as the blanket, first wall, or vacuum...
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Davide Laghi (Fusion For Energy)09/06/2026, 14:20Benchmarking and V&VOral
JADE is a python framework that makes it easy to automatically pre-process, run and post-process large numbers of neutronic simulations which are used for the Verification and Validation (V&V) of nuclear data libraries and Monte Carlo codes.
Last year, at the first edition of the “Fusion Neutronics Meeting”, the new architecture of JADE v4 was presented. The complete rewriting of the...
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Victor Lopez Ochoa (Universidad Nacional de Educación a Distancia (UNED))09/06/2026, 14:40Geometry, radiation transport, activation, multiphysics tools.Oral
Safe licensing and operation of future fusion reactions requires demonstrating material performance after extreme irradiation conditions. This needs to be demonstrated through material irradiation in a suitable neutron source facility under fusion-relevant conditions
IFMIF-DONES is an accelerator-based neutron irradiation facility, providing the necessary irradiation data for the...
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QingMing He09/06/2026, 15:00Uncertainty quantification.
In the design of fusion blanket systems, the Tritium Breeding Ratio (TBR) is a key parameter that characterizes the blanket's ability to sustain tritium. The accuracy of its calculation largely depends on the reliability of nuclear data and computational methods. Based on the Monte Carlo software NECP-MCX, this study uses the differential operator perturbation method to conduct a sensitivity...
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Virginie Lombardi (DIEE Department, La Sapienza University of Rome, 00186, Roma, Italy)09/06/2026, 15:50Benchmarking and V&VOral
Concrete is a widely used material in nuclear facilities, combining structural mechanical performance with effective radiation shielding capability. The design of bioshields and reactor buildings strongly relies on the ability of computational tools to accurately predict neutron and photon transport. In this context, the validation of numerical codes against experimental benchmarks is...
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Andrea Colangeli (ENEA)09/06/2026, 16:10Nuclear data development and experimentsOral
In 2025, the EUROfusion concrete shielding experiment was conducted at the 14 MeV Frascati Neutron Generator (FNG) facility at ENEA Frascati with the aim of investigating neutron transport in concrete and assessing the capability of Monte Carlo codes to reproduce experimental results.
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Three types of active neutron detectors were employed: silicon carbide (SiC) detectors, GS20 Li-glass... -
Marta Campos Fornés (ATG Science & Engineering S.L.)09/06/2026, 16:30Benchmarking and V&VOral
A comparative assessment between OpenMC 0.15.3 and MCNP 6.2 was performed on a three-section concrete labyrinth experiment from the ICSBEP database. The already existing MCNP benchmark model was converted to OpenMC and mesh-based weight windows were generated using the MAGIC method.
Neutron transport from a 252Cf spontaneous fission source was simulated, with neutron flux computed at...
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Alexander Koen (Thea Energy)10/06/2026, 12:30Geometry, radiation transport, activation, multiphysics tools.Oral
The development of an automated, parametric workflow to generate high-quality neutronics meshes from complex source geometries remains a key practical challenge in fusion neutronics. These workflows are particularly challenging given the need for element quality, metadata tracking, and mesh conformity throughout a multi-stage pipeline.
Stellarmesh is an open-source library developed at Thea...
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Juan García Bueno10/06/2026, 12:50Geometry, radiation transport, activation, multiphysics tools.Oral
Neutronics simulations in fusion facilities are done typically with Monte Carlo radiation transport tools like MCNP. While these tools use geometries based on Constructive Solid Geometry (CSG), fusion facilities are typically modelled as CAD models using the B-rep (boundary representation) system. The most successful approach to overcome this limitation is CAD model conversion into CSG models....
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Dr Jonathan Walg (marvel fusion)10/06/2026, 14:10Geometry, radiation transport, activation, multiphysics tools.Oral
High‑reliability neutronics simulations are a critical component in the design and optimization of fusion systems. However, the complexity of modern Monte Carlo tools such as OpenMC often presents a significant barrier to their efficient use within fast, iterative engineering workflows. In this contribution, we present a user‑friendly application developed at Marvel Fusion that simplify and...
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Roman Afanasenko (Karlsruher Institut für Technologie (KIT))10/06/2026, 14:30Oral
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Mark Fortuna (University of Ljubljana; "Jožef Stefan" Institute)10/06/2026, 14:50Benchmarking and V&VOral
In this work, we describe how experiments where the energy response function and the angular response function of a neutron REM counter were modified, led to the improvement and validation of the computational model of the TCV facility. Due to an upgrade of the plasma heating system at TCV and a subsequent order-of-magnitude increase in neutron production, an upgrade of the radiological shield...
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Tom Berry (UKAEA)11/06/2026, 10:00Geometry, radiation transport, activation, multiphysics tools.Oral
The IFMIF-DONES accelerator will accelerate deuterons up to 40 MeV in order to generate fusion-like neutron fluxes for materials studies. Deuterons will be lost along the beamline, in scrapers and collimators, in the beam dump, and in d-Li reactions at the target. These deuterons and the neutrons produced in reactions may activate materials, particularly in components close to the beamline....
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Alberto Bittesnich (ATG Europe (F4E))11/06/2026, 10:20Geometry, radiation transport, activation, multiphysics tools.Oral
The decay of radioactive nuclides activated during the operation of nuclear fusion reactors represents one of the main safety concerns, leading to worker exposure during shutdown and maintenance phases as well as damage to critical electronics. For this, safety demonstrations of fusion reactors like ITER require a precise assessment of the Shut Down Dose Rate (SDDR). In recent years, the...
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Javier Alguacil (UNED)11/06/2026, 11:10Uncertainty quantification.Oral
Nuclear analyses performed using Monte Carlo (MC) radiation transport codes are affected by stochastic uncertainty arising from the probabilistic sampling of particle histories. While formal mathematical convergence cannot be guaranteed, MC transport codes provide statistical estimators—such as the relative stochastic uncertainty—that allow the assessment of result reliability. Compliance with...
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Prof. Wen Yin (Harbin Engneering University)11/06/2026, 11:30Nuclear data development and experimentsOral
Nuclear response cross-sections, including KERMA (Kinetic Energy Release in Materials) factor, displacement damage cross-section and gas production cross-section, are critical nuclear data for nuclear heating, atomic displacement and H/He gas production. KERMA factor and displacement damage cross-section are researched at Harbin Engineering University recently for some potential...
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Dr Alberto Previti (ENEA)11/06/2026, 11:50Activation-related issuesOral
Activation Corrosion Products (ACP) are one of the more challenging aspects of radiation protection assessment for the safety analysis nuclear installations. The generation, transport, and deposition of ACP in cooling circuits require powerful simulation solvers capable of representing the interplay of different physical phenomena raging from thermal-hydraulic, chemistry, neutron activation,...
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Xiaokang Zhang (Institute of Plasma Physics, Hefei Institutes of Physical Science, Chinese Academy of Sciences)11/06/2026, 12:10AI and ML use for neutronicsOral
Machine-learning surrogates for coupled neutronics–activation calculations (OpenMC + FISPACT-II) reduce per-sample evaluation time from ~40 min to below one second, making rapid blanket design iteration feasible. Point predictions, however, do not suffice for safety-critical decisions. Activation inventory, decay heat, and contact dose rate span more than six orders of magnitude across time...
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