The laboratory actively participates in research and computational work on neutron diagnostics development and gamma ray analysis in fusion energy projects such as DEMO, ITER, JT-60SA, IFMIF-DONES, as well as in experiments involving neutron generators.
The team performs Monte Carlo radiation transport calculations using the MCNP code. This work includes modeling complex 3D geometries and calculating nuclear responses such as neutron and gamma ray fluxes, nuclear heating, atomic displacements (DPA), gas production, and activation of materials and liquids. The results are applied, among other uses, to the design and analysis of diagnostic devices and systems, optimization of designs, evaluation of component durability, shielding and radiation safety assessment, and preparation for future experiments and operation of nuclear fusion devices.
The team has experience in generating Monte Carlo simulation models from CAD geometry for components and entire fusion plant systems. This includes critical elements such as the DEMO divertor, limiters, and electron-cyclotron components; IFMIF-DONES structures such as the neutron beam tube, shutter, and duct (R160); and JT-60SA diagnostic systems including the VUV spectrometer, Thomson Scattering Trolley, and Pellet Launching System (PLS). Advanced tools such as SuperMC, GEOUNED, SpaceClaim, and RadModeling are used to convert solid CAD models into detailed neutronics representations for particle-transport calculations. To enhance computational efficiency and accuracy in particle transport and shielding simulations, the team applies variance-reduction techniques with the ADVANTG code.
In addition, the FISPACT-II code is used for activation calculations. The research focuses on the analysis of the evolution of the isotopic composition of the materials under consideration and the determination of their activity, decay heat and radiation dose rates. These activation results are used to determine waste classification by evaluating the radiological levels, material properties, and compliance with applicable regulatory requirements, ensuring proper handling, storage, and disposal strategies.
The team participates in the design of diagnostics for various fusion devices, including a neutron camera for the ITER tokamak and bolometric diagnostics for the COMPASS-U tokamak. Numerical tools for the reconstruction of one- and two-dimensional radiation emission distributions based on Tikhonov Regularization, Fisher Information Minimization, Maximum Entropy and Maximum Likelihood methods were developed. The developed methodology is used to analyze the distribution of the neutron emission, electromagnetic radiation, as well as the neutron spectra.
The laboratory has modern measurement facilities that enable neutron activation analysis to be carried out. Gamma spectrometry measurements allow for the identification of radionuclides formed in samples and the determination of their activity. The equipment includes an anti-coincidence system with a semiconductor HPGe detector (Canberra) featuring a resolution of 1.76 keV at 1332 keV energy and a relative efficiency of 30%, as well as a NaI scintillator (3" × 3"). The experimental system is housed in a 15 cm thick lead shield with low Pb-210 isotope content, lined internally with a layer of copper.
The laboratory also uses specialized software for data acquisition and analysis – GENIE 2000 – and dedicated tools for performance calibration: LabSOCS and ANGLE 5. It also includes two multigamma sources and Am–Be neutron sources with 185 GBq and 370 MBq activities.
