Reactor Control Panel
Map view and evaluation of radiative situation monitoring

Main directions of research, development of new safety methodologies

 

  • Development of new advanced methodologies corresponding to the current state of development (e.g. "best-estimate" approach based on the statistical evaluation of the evaluated results considering the uncertainties of the input data, computational models, correlations,  uncertainties on NPPs, etc.);
  • Development and application of coupled versions of computer programs;
  • Development of advanced "Trade-off" methodologies for solution of safely operational restrictions;
  • Verification of safety acceptance criteria on experimental databases;
  • Validation of computational programs on experimental facilities;
  • Development and application of CFD computational programs for analysis of media behavior in circuits of nuclear power plant, containments and fuel assemblies;
  • Support planning and evaluation of thermohydraulic experiments;
  • Conceptual studies on nuclear safety.

 

Safety Analyses

 

 

  • "Best-estimate" analyses of the damage to the nuclear fuel cladding and evaluation of the fission product release to the coolant;
  • 3D FEM modeling of fuel rods, respectively fuel assemblies;
  • Involvement in international programs organized by ECand OECD / NEA in the field of experimental research on fuel behavior in operational or DBA conditions.

 

  • Development of methodologies for advanced computational tools severe accidents;
  • Validation of integral computational tools (MELCOR, ASTEC, MAAP5-VVER) on experiments;
  • Development of own tools for processing input models based on graphical data;
  • Development of tools for evaluating the results of severe accident analysis for reactor applications and validation exercises;
  • Involvement in international research programs organized by the EC or OECD / NEA, and in OECD / NEA / ISP analytical exercises in many areas of severe accident phenomenology - eg. core degradation, hydrogen behavior, hydrogen deflagration, fission product behavior, evaluation of source terms, and minimization of uncertainties in the prediction of a severe accident.
Severe accidents and thermomechanics
  • Development of methodologies and tools in the field of radiation safety and emergency preparedness of nuclear power plants;
  • Development of tools for modeling the spread of radioactive substances to the environment and prediction of radiation effects;
  • Development of tools for modeling and visualization of the terrain radiation load and the assessment (prediction) of radiation doses to plant staff;
  • Development of 3D models of exteriors and interiors of the radiation source, visualization of the propagation of harmful substances into the environment;
  • Development of simulation tools and methods using virtual reality for planning and optimization of interventions in the NPP complex in case of a severe accident.


  • Radiation safety and preparedness
  • +420 266 172 446
  • Vladimir.Fiser@ujv.cz

 

  • Development of procedures for quantification of probabilistic parameters of risk assessment models for inadequate data, including application of Bayesian approache and use of expert judgment;
  • Monitoring the risk of nuclear and non-nuclear operations specifically focused on external events;
  • Development of methods of assessing the reliability of human in the conditions of the operation of complex technology under dynamically changing conditions;
  • Methods of collecting and evaluation of data from the training of the operators on full scope simulator;
  • Adaptation of probabilistic safety assessment methods to non-nuclear technologies;
  • Cost-benefit analyses methods for safety-enhancing applications;
  • Incorporaton if natural events into the risk models of complex technology;
  • Methodology of modeling and quantification of failure of digital information and control systems.
Reliability and risks - Jaroslav Holý
  • Adaptation of probability assessment methods of complex technology on reliability issues;
  • Reliable-oriented maintenance methodology (RCM);
  • Developing methods of assessing the reliability of a human within the conditions of the operation of complex technology under dynamically changing conditions;
  • Methodological support for analysis and estimation of probabilities of multiple faiulures with common cause;
  • Methodology of probability modeling of reliability of digital control and safety systems.
Reliability and risks - Jaroslav Holý
  • Development of tools for visualizing the results of severe accidents for the purpose of training of NPP staff
  • Development of virtual 3D models of nuclear power plant systems and components for staff training purposes
  • Development of virtual 3D models for decommissioning planning and optimization and dismantling practice of contaminated equipment

 

Division of Nuclear Safety and Reliability
  • Address:  ÚJV Řež, a. s., Hlavní 130, Řež, 250 68 Husinec, Czech Republic
  • Phone: +420 266 173 558     
  • Fax: +420 220 941 029
  • E-mail: safety@ujv.cz