- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Fusion materials and technologies
- Magnetic confinement fusion research
- Radiation Detection and Scintillator Technologies
- Nuclear Materials and Properties
- Laser-Plasma Interactions and Diagnostics
- Cold Fusion and Nuclear Reactions
- Atomic and Subatomic Physics Research
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Radioactive contamination and transfer
- Anomaly Detection Techniques and Applications
- Particle Detector Development and Performance
- Fault Detection and Control Systems
- Advanced X-ray Imaging Techniques
- Medical Imaging Techniques and Applications
- Advanced X-ray and CT Imaging
Institute of Nuclear Physics, Polish Academy of Sciences
2015-2024
Culham Centre for Fusion Energy
2017
Culham Science Centre
2017
This paper details progress in experimental characterisation work at JET for the long-term irradiation station, conducted as part of a project to perform activation experiments using ITER materials. The aim is take advantage significant 14 MeV neutron yield expected during operations irradiate samples materials that will be used manufacturing tokamak components, such Nb3Sn, SS316L steels from range manufacturers, SS304B, Alloy 660, W, CuCrZr, OF–Cu, XM-19, Al bronze, NbTi and EUROFER....
Several experimental activities have been conducted within the 'ACT' sub-project under EUROfusion WPJET3 programme with purpose to ultimately irradiate ITER materials JET D–T neutron environment. The latest results of these are presented in this work. include: poloidal field coil jacket samples and toroidal radial closure plate steels, EUROFER 97-2 steel, W CuCrZr from divertor, Inconel 718, 316L stainless steel for blanket modules vacuum vessel forging samples. here include gamma...
A high resolution neutron spectrometer (HRNS) system has been designed as a diagnostic tool for ITER. The HRNS is dedicated to measurements of time resolved energy spectra both ...
Abstract This paper presents a set of diagnostics dedicated to PF-24 - new medium size plasma focus (PF) device built and operated at the Institute Nuclear Physics Polish Academy Sciences (IFJ PAN). The can operate energy level up 93 kJ charging voltage 40 kV. Each condenser is connected with specially designed spark gap very small jitter, which ensures high effi ciency low current rise time. working parameters generator make it suitable tool for testing detection systems be used in fusion...
In the 2019 C38 Deuterium-Deuterium campaign at JET several different ITER-relevant materials and dosimetry foils were irradiated in a specially designed long-term irradiation station located inside vacuum vessel with purpose of testing activation ITER by fusion neutrons. The samples exposed to neutron fluence 1.9E14 n/cm 2 during discharges performed experimental over period 5 months. Gamma ray spectroscopy measurements on determine long-lived isotopes samples. Monte Carlo computational...
A fast-neutron pinhole camera based on small-area (5mm × 5 mm) BCF-12 scintillation detectors with nanosecond time resolution has been designed. The is dedicated to the investigation of spatial and temporal distributions DD neutrons from Plasma Focus (PF-24) source. geometrical parameters have optimized in terms maximum neutron flux at imaging plane by means MCNP calculations. detection system consists four closely packed coupled via long optical fibres Hamamatsu H3164-10 photomultiplier...
Abstract This work presents the results following first irradiation of ITER materials samples in a tokamak D–T plasma environment operating at significant fusion power. The exposed to this nuclear Joint European Torus during DTE2 experimental campaign that took place 2021 include representative from various components such as poloidal field coil jacket samples, toroidal radial closure plate steels, EUROFER 97 steel, W and CuCrZr divertor, Inconel-718 316L stainless steel for blanket modules,...
In this paper, the possibilities to perform aneutronic fusion in Plasma Focus (PF) devices have been presented. For purpose, an idea of doping plasma by means laser ablation a solid boron target during discharge PF-24 was Some estimates made, based on processes occurring PF system with gas injection using fast valve, indicating that method allows generation hydrogen–boron plasma. The yield 11B(p,α)αα reaction calculated. results presented paper show is high enough register and measure alpha...
This work presents results of the calculations performed in order to predict neutron-induced activity structural materials that are considered be using at TPR spectrometer-one detection system High-Resolution Neutron Spectrometer for ITER. An attempt has been made estimate shutdown dose rates a Cuboid #1 and check if they satisfy ICRP regulatory requirements occupational exposure radiation ITER nuclear safety regulations areas with personal access. The were obtained by MCNP FISPACT-II calculations.
Eight documented tritiated targets were stored, as well some very old with unknown activity, in a room equipped an ING-114 14 MeV fast neutron generator. When the generator was running, irradiated deuterium beam. The aim of this work is to determine tritium content room's atmosphere, radiation exposure workers room. In study, isotopic exchange assumed. This means that from diffused into air, where it reacted immediately oxygen particles form vapour. These vapour molecules open vessels...
Plastic organic scintillators such as the blue-emitting BCF-12 are versatile and inexpensive tools. Recently, have been foreseen for investigation of spatial distribution neutrons emitted from dense magnetized plasma. For this purpose, small-area (5 mm × 5 mm) detectors based on scintillation rods Hamamatsu photomultiplier tubes were designed constructed at Institute Nuclear Physics. They will be located inside neutron pinhole camera PF-24 plasma focus device. Two different geometrical...
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