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Dr Sudhirsinh Vala (Institute for Plasma Research)08/06/2026, 17:00Nuclear data development and experimentsPoster
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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Mr Christopher Ashe (UKFE)08/06/2026, 17:00Facility nuclear design challengesPoster
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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Shanqi Chen (1)SuperSafety Science & Technology Co., Ltd., Hefei 230088, China; 2)International Academy of Neutron Science, Chongqing, 401331, China)08/06/2026, 17:00AI and ML use for neutronicsPoster
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, 17:00Neutron/gamma diagnostics and calibrationPoster
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, 17:00AI and ML use for neutronicsPoster
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, 17:00Activation-related issuesPoster
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, 17:00Geometry, radiation transport, activation, multiphysics tools.Poster
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, 17:00Geometry, radiation transport, activation, multiphysics tools.Poster
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, 17:00Radiation mappingPoster
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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Dr Domen Kotnik (Jozef Stefan Institute)08/06/2026, 17:00Activation-related issuesPoster
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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Samuele Castegnaro (ENEA)08/06/2026, 17:00Radiation mappingPoster
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, 17:00Breeding blanket optimisationPoster
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, 17:00Geometry, radiation transport, activation, multiphysics tools.Poster
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. -
Christopher Ehrich (Forschungs-Neutronenquelle Heinz Maier- Leibnitz (FRM II) Technische Universität München)08/06/2026, 17:00Facility nuclear design challengesPoster
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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Mr Kok Yue Chan (Department of Engineering Physics, Tsinghua University)08/06/2026, 17:00Geometry, radiation transport, activation, multiphysics tools.Poster
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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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...
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