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Dr Dieter Leichtle (Karlsruhe Institute of Technology (KIT))08/06/2026, 13:00
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Prof. Christoph Kirchlechner (Karlsruhe Institute of Technology (KIT))08/06/2026, 13:10
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Dr Ulrich Fischer (Retired, ex-KIT)08/06/2026, 13:30Invited
The development of Fusion Neutronics is closely related to Fusion Technology (FT) kicked-off in the 1970ies with the first tokamak reactor studies conducted then at the University of Wisconsin, Madison, in the US. Such studies necessitate the application of suitable computational tools, models and nuclear data to provide the nuclear responses required for assessing the nuclear performance of...
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G. Náfrádi08/06/2026, 14:00
G. Náfrádi1, S. Puthanveetil1, E. Polunovskiy1, G. Zeng1, G. Pedroche2, P. Martinez2, P. Guijosa2, N. Khvatkin2, A. Mayo2, L. Ruiz2, J. Alguacil2, V. López2, P. Sauvan2, R. Juárez2, R. Pampin3, D. Laghi3, M. Campos Fornés3, A. Bittesnich3, A. Cubí3, M. Di Giacomo3, M. Fabbri3, A. Kolšek3, T. Schioler1
1 ITER Organization, Route de Vinon-sur-Verdon - CS 90 046 - 13067 St Paul Lez Durance...
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Aljaz Kolsek (Fusion for Energy (F4E))08/06/2026, 14:30
In 2020, a high-fidelity 360° MCNP model of the ITER tokamak was developed by assembling seven replicas of the C-Model (a 40° sector of a regular vacuum vessel segment), integrating the 80° toroidal segment of the Neutral Beam Injector (NBI), and incorporating all available MCNP models of ITER ports, followed by targeted refinements. The resulting E-lite model represented a significant...
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Pol Guijosa (UNED)08/06/2026, 14:55
ITER will be a major step towards demonstrating the scientific and technological feasibility of nuclear fusion as a clean and safe energy source. It will operate the largest Tokamak ever built. The radiation fields expected in ITER, both during and after operation, make nuclear analyses particularly valuable. Some of these analyses constitute a significant part of the ITER Rapport Préliminaire...
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Alex Valentine (UKAEA)08/06/2026, 15:45Neutronics Strategies, Workforce and Knowledge Base managementOral
The Applied Radiation Technology group at the United Kingdom Atomic Energy Authority (UKAEA) comprises a group of experts in neutronics and radiometrics to support the delivery of fusion energy. The group has expanded significantly in recent years, driven by unprecedented investment in the UK fusion programme and the rapid growth of the international private fusion sector. This growth is...
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Marco Fabbri (Fusion For Energy)08/06/2026, 16:10Neutronics Strategies, Workforce and Knowledge Base managementOral
As per title.
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Flammini Davide (ENEA)08/06/2026, 16:35Activation-related issues
The Divertor Tokamak Test (DTT) facility will be constructed at the ENEA Frascati Research Centre to address the problem of power exhaust, one of the key challenges of the future fusion power plants. DTT is a medium-sized superconducting tokamak operating with a deuterium plasma and with a substantial level of external heating power, to reproduce the divertor heat loads foreseen for ITER and...
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Shanqi Chen (1)SuperSafety Science & Technology Co., Ltd., Hefei 230088, China; 2)International Academy of Neutron Science, Chongqing, 401331, China)08/06/2026, 17:00
To provide intelligent design and analysis in the fields of radiation shielding, material activation, and dose calculation, TopMC (multi-functional program for neutronics calculation, nuclear design and safety evaluation) has been developed. As an updated and extended version of SuperMC, TopMC focus on full-function and high-efficiency neutronics calculation, CAD/image-based accurate modeling...
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Marta Damiano (tor vergata university)08/06/2026, 17:00
Current neutron irradiation facilities cannot fully reproduce the complex radiation spectra expected in fusion tokamaks such as ITER. As a result, experimental qualification of components under fully representative ITER conditions is not yet achievable with conventional test infrastructures.
To address this gap, GENeuSIS (General Experimental Neutron System Irradiation Station) was...
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Jhovanna Garcia (ORNL)08/06/2026, 17:00
Deuterium-tritium fusion is often described as intrinsically low-waste, however ensuring that fusion components meet low-level waste (LLW) acceptance criteria under U.S. regulatory frameworks (10 CFR 61) requires coordinated control of impurity content and operating conditions. This study develops an accelerated surrogate framework to support that task by linking isotope-resolved waste...
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Chen Yang (Institute of Energy, Hefei Comprehensive National Science Center)08/06/2026, 17:00
Activated corrosion products (ACPs) are a key source term for shutdown dose rates and radioactive waste management in fusion reactors. In this paper, we focus on a burning plasma experimental tokamak and apply the CATE (Corrosion, Activation and Transport Evaluation) code to analyze four key systems: blanket first wall, shield block, vacuum vessel, and divertor. We calculate the evolution of...
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Timo Bogaarts (Eindhoven University of Technology)08/06/2026, 17:00
Neutronic engineering constraints significantly limit the stellarator design space by forcing a minimum coil-plasma distance compliant with sufficient tritium breeding ratio and fast flux shielding. Currently, these engineering constraints are taken into account by simply posing a minimum coil-plasma distance, independent of the specific coil or blanket design. Afterwards, a blanket is...
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Perry Young08/06/2026, 17:00
Full treatment of isomeric branching is important in predicting activation in high yield fusion generators. Here-to, OpenMC1 Deplete lacked energy dependent isomeric branching. Rather, pre-processed fixed branching ratios (BR) were stored for reactions on the chain. This work will present implementation of full energy-dependent isomeric branching in OpenMC, accomplished by leveraging UKAEA...
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Stefano Colombi (University of Milano-Bicocca)08/06/2026, 17:00
Collimated line-of-sight diagnostics such as the Radial Gamma Ray Spectrometer (RGRS) could be used for fusion power measurement at ITER. Compared with other approaches, such as fission chambers or activation foils, they offer the advantage of observing only the plasma section along a collimated line of sight, simplifying the calibration procedure by removing the need for complex neutronic...
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Samuele Castegnaro (ENEA)08/06/2026, 17:00
The Divertor Tokamak Test (DTT) is a new experimental facility designed to the study of plasma exhaust issues in a DEMO-relevant environment and to test different divertor configurations. During high-performance operation, DTT is expected to produce approximately 1.5e17 neutrons per second from D-D fusion reactions. In addition to that a non-negligible amount of neutrons produced from D-T...
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69. Neutronic and Structural Optimization of a Novel Pin-Type HCPB Breeding Blanket for the DEMO LARJin Hun Park (Karlsruhe Institute of Technology)08/06/2026, 17:00
This study introduces a novel Helium Cooled Pebble Bed (HCPB) Breeding Blanket (BB) design tailored for the DEMO Low Aspect Ratio (LAR) reactor. Despite the stringent constraints imposed by reduced fusion power and compact tokamak dimensions, the proposed design maintains the conventional pin-type architecture while achieving a sufficient Tritium Breeding Ratio (TBR) and superior internal...
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Dr Anna Wójcik-Gargula (Institute of Nuclear Physics Polish Academy of Sciences)08/06/2026, 17:00Activation-related issues
The High Resolution Neutron Spectrometer (HRNS) is designed for neutron diagnostics in ITER, where accurate measurements must be combined with careful assessment of radiation-induced activation of detector and structural components. Understanding the activation behaviour of diagnostic systems is essential for evaluating operational safety, maintenance requirements, and long-term radioactive...
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Jean-Christophe Trama (CEA Paris-Saclay)08/06/2026, 17:00
OPERA, a CEA Paris-Saclay initiative, gathers cutting-edge tools for fixed-source radiation transport. In the early stages, our goals are:
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• A 3D modeling tool, capable of CAD import and meshing;
• Enhanced hybrid capabilities, accelerating Monte Carlo fixed-source calculations with deterministic methods and offering standalone 3D deterministic calculations. -
Mr Kok Yue Chan (Department of Engineering Physics, Tsinghua University)08/06/2026, 17:00
The Reactor Monte Carlo (RMC) code, developed by the Reactor Engineering Analysis Laboratory (REAL) at Tsinghua University, is a continuous-energy Monte Carlo transport code that has been widely applied in reactor physics analyses. In recent years, its capabilities have been further extended to fusion neutronics applications. This work summarizes recent progress in the development and...
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Sara Abad Jiménez (IDOM)08/06/2026, 17:00
This work presents a systematic optimization study of neutron source shielding for a dedicated multilayer bunker designed to house a cylindrical inertial electrostatic confinement (IEC) neutron source within the framework of the LIBRA project. LIBRA aims to investigate lithium deuteride (⁶LiD) as a tritium breeding material for future nuclear fusion applications.
The bunker design must...
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47. W7-X neutronics simulations for new neutron diagnostics with application to fast-ion confinementRiccardo Brambilla (TU Eindhoven, IPP Max Planck)08/06/2026, 17:00Geometry, radiation transport, activation, multiphysics tools.
By the end of 2028 it is foreseen that the W7-X stellarator will switch from Hydrogen to Deuterium fuel, starting DD operation. The DD fusion reactions will lead to the production of 2.5 MeV neutrons together with fast Tritium nuclei which can themselves fuse with Deuterium thermal plasma creating 14 MeV DT neutrons.
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The detection of these two different species of neutrons, namely 2.5 MeV DD... -
Dr Jonathan Shimwell (Proxima fusion)09/06/2026, 09:00Neutronics Strategies, Workforce and Knowledge Base management
Fusion neutronics has long relied on tools built for fission, adapting transport codes designed around criticality calculations, borrowing finite-element meshers intended for structural analysis, and working around defaults tuned for reactor physics. With a growing fusion industry, increasing demand from private companies, and the reduction in development effort enabled by large language...
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Dr Vittorio Badalassi (ORNL)09/06/2026, 09:30
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Henry Marden (UK Atomic Energy Authority)09/06/2026, 10:00
The Spherical Tokamak for Energy Production (STEP) is a UK programme to design and build a prototype fusion energy plant. STEP is an ambitious programme that will demonstrate the ability to generate net energy, fuel self-sufficiency and a route to commercialisation of nuclear fusion.
The compact radial design of a spherical tokamak presents a significant neutronic design challenge for...
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Alexandre Sureda Croguennoc (IDOM)09/06/2026, 10:20
The efficient and accurate design of tritium breeder blankets is essential for the success of nuclear fusion reactors, playing a vital role in achieving optimal performance and safety. This study, developed within the LIBRTI programme funded by UK Atomic Energy Authority (UKAEA), introduces a comprehensive workflow that integrates parametric geometry generation, meshing, and multiphysics...
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Jonathan Naish (Type One Energy)09/06/2026, 11:10
Infinity Two is a 350 MWe fusion pilot power plant under development by Type One Energy, designed to be one of the first commercially viable stellarator based fusion energy systems. A central feasibility challenge for this advanced high field stellarator concept is the development of an efficient and fully integrated blanket system. Consequently, the design and optimisation of the breeding...
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Žiga Štancar (UK Atomic Energy Authority)09/06/2026, 11:40Geometry, radiation transport, activation, multiphysics tools.
In the contribution we present a framework for computing realistic plasma neutron source models for ITER, based on coupling between the plasma transport code JINTRAC and the fusion kinematics code DRESS, and demonstrate its application to the MCNP neutron transport code. This allows capturing plasma events throughout the whole predicted scenario trajectory, including transients, and their...
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Ylenia Kogovšek Žiber (Jožef Stefan Institute (JSI))09/06/2026, 12:00
Accurate evaluation of shutdown dose rate (SDDR) represents a key requirement in fusion reactor design and operation and is essential to ensure personnel safety throughout the entire lifetime of fusion facilities, in particular during maintenance and their decommissioning. SDDR tools have been developed for this purpose, among which JSIR2S, developed at the Jožef Stefan Institute, implements...
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Georg Schnabel (IAEA)09/06/2026, 12:20Nuclear 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... -
Davide Laghi (Fusion For Energy)09/06/2026, 12:50
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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Enrique Miralles-Dolz (Princeton Plasma Physics Laboratory)09/06/2026, 14:10Nuclear 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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Victor Lopez Ochoa (Universidad Nacional de Educación a Distancia (UNED))09/06/2026, 14:30Geometry, 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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Mohan Wang09/06/2026, 14:55Uncertainty 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, 15:50
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, 16:30
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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Miguel Macias (IFMIF-DONES Consortium)10/06/2026, 09:00
The properties of materials for nuclear fusion applications are not yet fully understood under the neutron irradiation conditions foreseen in future fusion reactors. IFMIF DONES is designed to address this gap by providing neutron irradiation conditions representative of fusion environments. IFMIF DONES is an accelerator-based neutron source composed of a deuteron injector, a Radio Frequency...
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ANTONIO JESUS LOPEZ REVELLES (UNIVERSIDAD NACIONAL DE EDUCACION A DISTANCIA (UNED))10/06/2026, 09:20
Radiological dose mapping in the IFMIF-DONES accelerator system poses a demanding neutronics problem because the radiation field is not governed by a single source term, but by the superposition of multiple contributions with different physical origins and spatial distributions. During beam-on, biological dose and absorbed dose in silicon are largely driven by neutrons and photons produced in...
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Ms Qi Yang (Iternational Academy of Neutron Science), Mr Jun Gao (International Academy of Neutron Science), Mr Wei Wang (International Academy of Neutron Science)10/06/2026, 09:40
Neutron sources are the important experimental platform for the R&D of advanced nuclear energy systems, especially for the development for fusion systems. Series High Intensity D-T Steady Neutron Sources (HINEG) have been developed in China for different missions including neutronics design validation, materials & components irradiation test, nuclear waste burning and nuclear technology...
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Aljaž Čufar (Jožef Stefan Institute)10/06/2026, 10:00Facility nuclear design challenges
In recent years, a Volumetric Neutron Source (VNS) has been developed within EUROfusion with the aim of first demonstrating feasibility and then designing a machine that would reduce risk for the successful operation of teh demonstration fusion power plant DEMO. This would be achieved by designing and constructing a facility where crucial nuclear technologies, such as the tritium breeding...
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Jin Hun Park (Karlsruhe Institute of Technology)10/06/2026, 10:20
For optimize nuclear fusion reactor designs, the need for detailed neutronics analysis is one of the important points, especially in terms of shielding performance and the overall impact on tokamak and facility safety. This study presents an extensive neutronics simulation of a Volumetric Neutron Source (VNS) focusing on the inboard area of a tokamak, coupled with a sector-based evaluation of...
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Raul Luís (Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Universidade de Lisboa, Av. Rovisco Pais 1, 1049-001 Lisboa, Portugal)10/06/2026, 11:10
As tokamak operation advances toward long-pulse and steady-state regimes, plasma-facing diagnostics will accumulate increasing nuclear loads over the lifetimes of the facilities. In such environments, the possibility of diagnostic failure due to neutron exposure cannot be excluded. Therefore, the design strategy for DEMO diagnostics has favoured robust front-end components compatible with...
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xilong Tong (University of Science and Technology of China)10/06/2026, 11:30
Fusion-fission hybrid reactors represent a promising pathway for future energy supply. However, the feasibility of this technological route has yet to be validated through a Test Blanket Module (TBM)-scale experiment, and comprehensive theoretical designs are still required to guide such experimental efforts. In this study, an innovative TBM design containing spent fuel from Pressurized Water...
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Fabio Moro (ENEA, Nuclear Department)10/06/2026, 11:50Neutronics Strategies, Workforce and Knowledge Base management
The neutronics activities carried out by ENEA in support of the ITER, DEMO, DTT, and EUROfusion programmes span a over a wide range of topics related to nuclear fusion technology. These activities include advanced three-dimensional neutronics analyses, activation calculations, and radiation shielding studies as well as experimental campaigs dedicated to the validation of codes and nuclear...
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Simone Noce (ENEA)10/06/2026, 12:10Activation-related issues
The wetted surfaces of water-cooled loops in nuclear reactors release corrosion products (CP) which, under neutron irradiation, become activated corrosion products (ACP), representing a major radiological concern. Their behavior is governed by complex multi-physics interactions involving neutronics, activation, corrosion, chemistry, and thermo-fluid dynamics. While ACP assessment in fission...
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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, 14:30
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Mark Fortuna (University of Ljubljana; "Jožef Stefan" Institute)10/06/2026, 14:50
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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Dr Sudhirsinh Vala (Institute for Plasma Research)10/06/2026, 15:10Nuclear data development and experimentsOral
A comprehensive series of neutron irradiation experiments were carried out at the Institute for Plasma Research using a 14-MeV neutron generator to support fusion technology development, nuclear data validation, and material qualification under high-radiation environments. Key investigations included neutron-induced reaction cross-section measurements for isotopes of Sb, Zr, Sn, Sr, and Re at...
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Dr Iole Palermo (Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (CIEMAT), Madrid, Spain)10/06/2026, 16:00Invited
Interest in stellarator-based fusion power plants has grown considerably within the fusion community, positioning stellarators as a promising alternative to tokamaks and motivating efforts toward their technological maturity and reactor readiness. Within this expanding stellarator ecosystem, the EUROfusion programme provides a coordinated, reactor-oriented, and physics-based framework for...
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Tim Eade (UKIFS)11/06/2026, 09:00
The Spherical Tokamak for Energy Production (STEP) is an ambitious programme to generate net energy from fusion and to stimulate an industry that will help prove its commercial viability. It will achieve this by producing a prototype tokamak powerplant to provide energy to the grid.
The project is currently refining the overall plant architecture, plasma configuration and supporting...
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Dr Egor Vezhlev (gauss-fusion)11/06/2026, 09:30
Gauss Fusion GmbH has recently established an open-source software-based workflow for stellarator neutronics that enables comprehensive and reproducible simulations of full-device stellarator machines. The framework integrates established community tools, including STELLOPT for magnetic equilibrium optimization, ParaStell for homogenized geometry generation, Coreform Cubit© and Gmsh for models...
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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, 11:10
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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Dr Alberto Previti (ENEA)11/06/2026, 11:35
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, 12:00
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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Urszula Wiącek (Institute of Nuclear Physics Polish Academy of Sciences, Radzikowskiego 152, PL-31342 Krakow, Poland)11/06/2026, 12:25Neutron/gamma diagnostics and calibration
The Start-Up Monitoring Module (STUMM) is currently under development as a dedicated calibration and diagnostic system intended for the commissioning stage of IFMIF-DONES. The module will be positioned in proximity to the neutron source, within the irradiation zone used for material testing. Its main purpose is to enable accurate characterization of neutron source parameters and prevailing...
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Irene Álvarez Castro11/06/2026, 12:45
The materials proposed for nuclear fusion applications have yet to be fully characterized under the neutron irradiation conditions expected in future fusion reactors. IFMIF DONES (International Fusion Materials Irradiation Facility – DEMO Oriented NEutron Source) has been conceived to address this challenge by irradiating materials under neutron conditions representative of those found in...
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Dr Arkady Serikov (Karlsruhe Institute of Technology (KIT))11/06/2026, 14:10
This work presents computational neutronic analyses performed for the safety of the IFMIF-DONES Target Assembly components and parametric analyses of the Neutron Beam Tube and Shutter (NBT&S) diameter to increase the collimated neutron flux at the entrance to Complementary Experiments Room 160 (CER R160). The IFMIF-DONES project is under construction in Spain. The radiation transport parallel...
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Kohki Kumagai (QST)11/06/2026, 14:30
As part of the IFMIF/EVEDA project, the Linear IFMIF Prototype Accelerator (LIPAc) was constructed at Rokkasho, Japan, and a Superconducting Radio-Frequency (SRF) accelerator has been installed for the upcoming 9 MeV deuteron beam campaign. In the previous 5 MeV beam experiments, radiation transport analyses using MCNP relied on manually created geometry models including only major components....
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Saerom Kwon (National Institutes for Quantum Science and Technology (QST))11/06/2026, 14:50Nuclear data development and experiments
Lithium targets are commonly employed to produce “fusion-relevant” neutrons in fusion technology validation facilities, where proton-lithium (p-Li) reactions serve as the primary neutron source. Accurate neutron production cross sections are critical for facility designs, shielding calculations, and dosimetry. However, the quality and consistency of available proton-induced lithium nuclear...
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Mr Aleksei Pankratenko (ITER RF DA)11/06/2026, 15:40
The main goal of ITER operation is demonstration of fusion power reaching values up to 10 times greater than the supplied plasma heating power. This demonstration relies on the set of neutron diagnostics capable of measuring the neutron yield with 10% accuracy and of providing reliable data stream for regulatory purposes. The specified accuracy is planned to be achieved through in situ neutron...
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Dr Bjoern Lehnert (TU-Dresden)11/06/2026, 16:00
The TU Dresden Neutron Generator (TUD-NG) is an accelerator-driven deuterium–tritium (DT) neutron source designed for fusion-relevant irradiation experiments. The facility delivers deuterium beams of several milliampere onto a water-cooled tritium target, producing neutrons via the 3H(d,n)4He reaction with energies around 14 MeV. The source is designed to reach neutron yields of up to 1012 n/s...
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Dr Nicola Fonnesu (ENEA)11/06/2026, 16:20
In late 80s-early 90s, two projects of accelerator-based 14-MeV neutron sources were conceived at the ENEA Research Center of Frascati, i.e., the Frascati Neutron Generator (FNG) and SORGENTINA, in response to specific needs of the scientific community involved in Controlled Thermonuclear Fusion. FNG (neutron strength up to 1.5x1011 s-1) was mainly to support the development and benchmark of...
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Bhargav Soni (ITER-India, Institute for Plasma Research)12/06/2026, 09:00
The monitoring of plasma impurity influx in ITER is facilitated by the X-Ray Crystal Spectrometer-Survey (XRCS-Survey) located in Equatorial Port-11. To ensure high-sensitivity X-ray collection, this diagnostic utilizes a windowless line-of-sight; however, this open optical path creates a direct path for significant neutron streaming toward the spectrometer assembly. This study evaluates the...
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28. Comprehensive modeling of activated water radiation sources of ITER Tokamak Cooling Water SystemDr Pablo Martínez Albertos (UNED)12/06/2026, 09:20
The activated water has been identified as a relevant radiation source in fusion facilities during plasma operation. In ITER, cooling water is activated near first-wall components due to the intense neutron exposure and carries the produced radioisotopes far from the irradiation region. This phenomenon generates complex radiation fields outside the bioshield, directly impacting on the design...
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11. From Tokamak to Research Reactor: Replicating JET Water Activation Experiment at KATANA FacilityJulijan Peric (Jozef Stefan Institute - JSI)12/06/2026, 09:40
Water activation plays a key role in fusion facilities, contributing to radiation fields, shutdown dose rates, and overall operational safety. High-energy neutrons produced during fusion reactions interact with oxygen and other elements in the coolant, generating short-lived activation products such as N-16 and N-17. These isotopes emit high-energy gamma radiation and neutrons, affecting...
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Alvaro Cubi (F4E)12/06/2026, 10:00
The Start of Research Operation (SRO) is the first nuclear operational phase of ITER, as defined in the ITER baseline research plan. During this phase, hydrogen and deuterium plasmas are operated at full magnetic field and plasma current, but with limited neutron production, with the primary objective of demonstrating machine integrity and nuclear safety prior to deuterium–tritium operation....
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Egor Afanasenko (ITER RF DA)12/06/2026, 10:20
ITER Divertor Neutron Flux Monitor (DNFM) is designed to measure the total neutron yield and the fusion power in a wide dynamic range (1014 to 3x1020 n/s). Each DNFM detector unit is comprised of 235U and 238U fission chambers with independent electrode systems coated with either 500, 50 or 5 mg of uranium, allowing it to cover the entire dynamic range of fusion power. This setup also provides...
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Yuefeng Qiu (KIT)12/06/2026, 11:10Geometry, radiation transport, activation, multiphysics tools.Oral
The stellarator has re-emerged as a promising fusion concept, supported by the success of Wendelstein 7-X. Within EUROfusion, the HELIAS stellarator concept has previously been continuously developed. In addition, stellarator-based reactor concepts are increasingly emerging as a mainstream reactor concepts among private fusion companies worldwide, due to their grid-friendly operation and...
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Seonghee Hong (Korea Institute of Fusion Energy)12/06/2026, 11:30
The divertor is an essential component in fusion reactors and must operate under extreme thermal loads and intense particle flux conditions. Consequently, most divertor designs, including ITER, adopt a water-cooled tungsten (W) monoblock (MB) concept. For fusion devices currently under construction or planned, neutrons generated by fusion reactions represent a critical design factor alongside...
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Kun XU (ASIPP)12/06/2026, 11:50
With the upgrade of in-vessel components, heating systems and the construction of specialized tritium storage, injection and collection system, EAST Tokamak will be ready for a short D-T operation phase (weeks) embedded within longer D-D phases, by the end of 2026 or later. This report summarizes the radiation safety analyses conducted for this campaign, to address the satisfaction of...
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Bor Kos (Baker Hughes)12/06/2026, 12:10
Content in attached pdf.
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12/06/2026, 14:00
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Mr Christopher Ashe (UKFE)
Reactor system codes use reduced-order models to represent each key subsystem of the fusion power plant, such that rapid self-consistent evaluation of full fusion power plant concepts can be performed. Traditionally system codes must rely on fitted empirical data to estimate neutron transport and deposition. PROCESS is the primary systems code used by UKAEA, which could benefit from the...
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Gabriel Pedroche (UNED)
ITER will be a major step towards demonstrating the scientific and technological feasibility of nuclear fusion as a clean and safe energy source. It will operate the largest Tokamak ever built. The radiation fields expected in ITER, both during and after operation, make nuclear analyses particularly valuable. Some of these analyses are expected to support the update of ITER Rapport...
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Dr Domen Kotnik (Jozef Stefan Institute)
KATANA is a water activation facility installed at the Jožef Stefan Institute TRIGA Mark II reactor in Ljubljana, Slovenia. It was developed to investigate water activation processes relevant to future fusion systems such as ITER. The primary objective of KATANA is to perform benchmark-quality experiments, e.g. the validation of the state-of-the-art fluid activation codes, for which an...
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Christopher Ehrich (Forschungs-Neutronenquelle Heinz Maier- Leibnitz (FRM II) Technische Universität München)
A variety of medical and radio isotopes yields have been calculated in Eurofusion's Volumetric Neutron Source (VNS) Tokamak using Serpent burnup mode simulations. The VNS is uniquely suited for the task of medical isotope production due to the fact that it will undergo a high neutron fluence requiring relatively low tritium (<1kg/year) that can be supplied by existing CANDU reactors. The VNS...
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Prof. Wen Yin (Harbin Engneering University)Nuclear 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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