8–12 Jun 2026
Karlsruhe Institute of Technology, Campus north
Europe/Berlin timezone

Session

Neutron Source Facilities Design and Exploitation

9 Jun 2026, 11:30
FTU (Karlsruhe Institute of Technology, Campus north)

FTU

Karlsruhe Institute of Technology, Campus north

Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen

Description

Performance evaluation
Neutron/gamma diagnostics and calibration

Presentation materials

There are no materials yet.

  1. Žiga Štancar (UK Atomic Energy Authority)
    09/06/2026, 11:30
    Geometry, 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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  2. Sara Abad Jiménez (IDOM)
    09/06/2026, 11:50
    Performance evaluation
    Oral

    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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  3. Ylenia Kogovšek Žiber (Jožef Stefan Institute (JSI))
    09/06/2026, 12:10
    Benchmarking and V&V
    Oral

    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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  4. Miguel Macias (IFMIF-DONES Consortium)
    10/06/2026, 09:00
    Performance evaluation
    Invited

    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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  5. ANTONIO JESUS LOPEZ REVELLES (UNIVERSIDAD NACIONAL DE EDUCACION A DISTANCIA (UNED))
    10/06/2026, 09:20
    Radiation mapping
    Oral

    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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  6. 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/gamma diagnostics and calibration
    Oral

    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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  7. Urszula Wiącek (Institute of Nuclear Physics Polish Academy of Sciences, Radzikowskiego 152, PL-31342 Krakow, Poland)
    11/06/2026, 12:30
    Neutron/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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  8. Irene Álvarez Castro
    11/06/2026, 12:50
    Neutron/gamma diagnostics and calibration
    Oral

    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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  9. Dr Arkady Serikov (Karlsruhe Institute of Technology (KIT))
    11/06/2026, 14:10
    Facility nuclear design challenges
    Oral

    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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  10. Kohki Kumagai (QST)
    11/06/2026, 14:30
    Neutron/gamma diagnostics and calibration
    Oral

    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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  11. Saerom Kwon (National Institutes for Quantum Science and Technology (QST))
    11/06/2026, 14:50
    Nuclear 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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  12. Mr Aleksei Pankratenko (ITER RF DA)
    11/06/2026, 15:40
    Neutron/gamma diagnostics and calibration
    Oral

    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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  13. Dr Bjoern Lehnert (TU-Dresden)
    11/06/2026, 16:00
    Neutron/gamma diagnostics and calibration
    Oral

    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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  14. Dr Nicola Fonnesu (ENEA)
    11/06/2026, 16:20
    Performance evaluation
    Oral

    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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