Persons at STU
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Basic information about a final thesisAdditional informationAdditional information about the final thesis follows. Click on the language link to display the information in the desired language.
|Language of final thesis:||Slovak|
Parts of thesis with postponed release:
|Title of the thesis:||Application of Monte Carlo method in reactor physics|
|Summary:||Inaugural Dissertation deals with the problem of application of the Monte Carlo based transport code system MCNP5 in the field of reactor-physical, operational and safety analyses, in particular for VVER-440/V213 reactor units of the Mochovce and Jaslovské Bohunice V2 nuclear power plants. The work consists of five chapters, which present a short characterization of the Monte Carlo method and the code, developed complex and general geometrical and material model of the VVER-440 reactor in the MCNP5 program, its verification and validation process, as well as its usage in selected research and engineering areas. The first application presented in this work is the verification of isothermal and moderator temperature reactivity coefficient values in defined temperature range for the first fuel loading pattern of the 3rd and the 4th unit of the NPP Mochovce. The second area of focus is the determination of spatial weighting functions of ex-core detectors for VVER-440 units of the NPP Jaslovské Bohunice V2. All selected problems arose from scientific and research demands and found their utilization in practice of the SE, Inc. company, too.|
|Key words:||MCNP code , Monte Carlo method, Reactor core, Ex-core detector, Weighting function|
|–||Final thesis (final thesis appendices) unlimited|
|–||Reviews for final thesis unlimited|