Description
Fusion reactor design and safety
Facility nuclear design challenges
Radiation mapping
Breeding blanket optimisation
Activation-related issues
Occupational radiation exposure and ALARA
Radioactive waste management
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Aljaz Kolsek (Fusion for Energy (F4E))08/06/2026, 14:30Radiation mappingOral
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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Gabriel Pedroche (UNED)08/06/2026, 14:50Radiation mappingOral
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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Pol Guijosa (UNED)08/06/2026, 15:10Radiation mappingOral
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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Henry Marden (UK Atomic Energy Authority)09/06/2026, 10:00Breeding blanket optimisationOral
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, 10:20Breeding blanket optimisationOral
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, 10:40Breeding blanket optimisationOral
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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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, 10:20Facility nuclear design challengesOral
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, 11:10Oral
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, 11:30Facility nuclear design challengesOral
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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Bhargav Soni (ITER-India, Institute for Plasma Research)12/06/2026, 09:00Activation-related issuesOral
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, 09:20Radiation mappingOral
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, 09:40Activation-related issuesOral
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, 10:00Radiation mappingOral
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, 10:20Neutron/gamma diagnostics and calibrationOral
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, 11:30Facility nuclear design challengesOral
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, 11:50Occupational radiation exposure and ALARAOral
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, 12:10Benchmarking and V&VOral
Content in attached pdf.
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