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Internship

Department of Nuclear reactors offers Internship and Training in fields related to nuclear reactors, detection, proliferation, nuclear materials, nuclear safety, nuclear security and others. Hands on Internship program is tailored to participant background and needs. Every year, approximately 10 to 15 nuclear engineering internships are hosted by the Department. Internship length vary from few weeks up to one year. Interns have usually background in nuclear, however interns for safeguards are often with non-engineering background, so engineering background is not required.

Areas offered

Areas offered corresponds to our reseach areas described in R&D page. Following list presents examples of areas that hosts interns most often:

  • reactor core calculation
  • nuclear safety and security/safeguards
  • reactor core design
  • nuclear material proliferation
  • nuclear materials
  • detector design
  • radiation detection

How to apply

For summer 2026, please contact directly guarantor for topic you like. He or She will reply. Topics that are closed (interns were selected) are marked closed. 

Funding

Students are usually paid by stipend from home institution, EU or other sources. However, this matter is very individual. For more details, please contact our internship coordinator.

Topic offered

Topics will added during January 2026.

Name Summary Duration Contact person Status
Deconvolution of HPGe Gamma Spectra Using Neural Networks Development and validation of neural network models to perform deconvolution of gamma spectra measured by an HPGe detector. The training data will be pre-calculated and provided by the supervisor. Applicants are expected to have prior experience with programming neural networks. 05–09/2026 (can be shorter, but min. 3 months). Ondřej Huml (This email address is being protected from spambots. You need JavaScript enabled to view it.)  
Safeguards by RMS The Department of Nuclear Reactors operates a nuclear reactor and therefore has some storage of nuclear fuel. The intern should try to analyze data available from the radiation monitoring system (RMS) in order to track nuclear material around the facility and analyze the possibility to use it for safeguard activities. 05–09/2026 (can be shorter, but min. 3 months). Ondřej Novák (This email address is being protected from spambots. You need JavaScript enabled to view it.)  
SMR siting assessment The SMR positioning has specific challenges and therefore it is necessary to conduct an analysis of external hazards and adjust the requirements. The intern should work on an analysis of sitting requirements related to external hazards. No previous experience needed. 05–09/2026 (can be shorter, but min. 3 months). Ondřej Novák (This email address is being protected from spambots. You need JavaScript enabled to view it.)  
Serpent/PARCS Full-Core Model Creation for the LDR lite Benchmark This project focuses on establishing a validated, two-step neutronics simulation platform for the LDR lite benchmark, representing a key step in the design and licensing of the LDR-50 SMR. Previous experience with reactor physics and Neutron-Physical modelling is required. The work involves creating a high-fidelity, explicit core model within the Serpent Monte Carlo code to generate accurate, homogenized, multi-group nuclear cross-sections and discontinuity factors. These Serpent-derived data are then implemented into the PARCS nodal diffusion code to construct the full-core model. Verification involves executing steady-state calculations (e.g., k_eff, power peaking factors) and systematically comparing the PARCS results against the high-fidelity Serpent reference solutions as defined by the LDR lite benchmark specifications. Experience with Serpent/PARCS and programming (e.g., Python) for results evaluation is appreciated but not required. 05–09/2026 (can be shorter, but min. 3 months). Ondřej Lachout (This email address is being protected from spambots. You need JavaScript enabled to view it.)  
Influence of Axial Diffusion and Eddington Factors on Neutron Physical Calculations This project investigates advanced methods for improving the accuracy of low-order deterministic reactor simulations by incorporating transport corrections, with the goal of producing a scientific publication. The methodology involves using the Serpent Monte Carlo code to generate Axial Diffusion Factors and Eddington Factors, which will be implemented in the PARCS model. The study will quantify the influence of these factors on reactor parameters using Serpent full-core calculations as reference. Experience with reactor physics and modelling is required; programming experience is appreciated but not necessary. 05–09/2026 (can be shorter, but min. 3 months). Ondřej Lachout (This email address is being protected from spambots. You need JavaScript enabled to view it.)  
Effect of moderator-fuel ratios on prompt period of subcritical reactor VR-2 The project focuses on simulations and experiments with the VR-2 subcritical reactor core for different moderator-fuel ratios. The goal is to study the effect of moderator-fuel ratios on the prompt period of the subcritical reactor. 05–09/2026 (can be shorter, but min. 3 months). Jan Rataj (This email address is being protected from spambots. You need JavaScript enabled to view it.)  
Macroscopic Cross-Section Preparation and History Effect Evaluation for the APR1000 Core Model This project focuses on the development of a full-core neutronic and thermal-hydraulics coupled calculation model for the APR1000 reactor. The Serpent2 neutronic calculation code will be used for the preparation of macroscopic cross-sections and the analysis of history effects during nuclear fuel burnup. The resulting model will be valuable for both educational purposes and optimization efforts. Models of the square fuel assembly and core geometry are particularly important in the context of the construction of new nuclear power plants in the Czech Republic. 05–08/2026 (minimum 3 months, with the possibility of extension). Pavel Suk (This email address is being protected from spambots. You need JavaScript enabled to view it.)  
Core Simulator Startup Sequences Analysis This project involves the development of methodologies for the physical and engineering startup processes of the Korean APR1000 power plant. The Czech Technical University in Prague has a unique opportunity to operate a real power plant core simulator, CoSi, which was obtained through international cooperation with Korean partners. This APR1000 core simulator plays a key role in the education of future nuclear reactor physicists and power plant staff. Students will develop methodologies for reactivity measurement, control rod calibration, and other measurements important for nuclear power plant operation. Part of the project will focus on simulating these methodologies on the core simulator and analyzing their benefits. 05–08/2026 (minimum 3 months, with the possibility of extension). Pavel Suk (This email address is being protected from spambots. You need JavaScript enabled to view it.)  
Analysis and Development of Nuclear Fuel for Soluble-Boron-Free Reactors This project focuses on the analysis and development of a new nuclear fuel design for soluble-boron-free (SBF) nuclear reactors. SBF reactors do not use soluble boron in the moderator to compensate for long-term reactivity changes due to fuel burnup. Instead of a homogeneous absorber dissolved in the coolant, reactivity control is achieved using control rods, and additional compensation is provided by burnable absorbers incorporated directly into the fuel. The project will first analyse the temperature reactivity feedback coefficients of a reference (standard) nuclear fuel design. Based on these results, an optimisation of the water-to-uranium ratio will be performed. Subsequently, the burnup behaviour and kinetics of the burnable absorbers will be analysed and parametrised. The final outcome of the analysis will be a set of simple interpolation tables providing the fuel assembly reactivity as a function of power level, burnup, initial enrichment, and burnable absorber parameters. These interpolation tables will support the core loading pattern design for an SBF small modular reactor (SMR). 05–08/2026 (minimum 3 months, with the possibility of extension). Pavel Suk (This email address is being protected from spambots. You need JavaScript enabled to view it.)