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Subchannel analysis of VVER-100 reactor core
Bednář, Michal ; Petrosyan, Taron (referee) ; Katovský, Karel (advisor)
This master’s thesis deals with boiling crisis and with departure from nucleate boiling ratio. This thesis explains terms like the boiling crisis in nuclear reactors and the thesis deals with individual parameters of the reactor core, which have an impact on departure from nucleate boiling ratio. After that, the thesis deals with subchannel analysis and describes basic mathematical and physical models of the chosen subchannel program. The thesis then processes, with the ALTHAMC12 subchannel program, the chosen parameters and their impact on departure from nucleate boiling ratio. The conclusion of the diploma thesis deals with the evaluation of the best and worst calculated combination.
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Analysis Of Various Candidate Salts For Molten Salt Reactor Application By Mcnp Software
Petrosyan, Taron
In present study, the model of Molten Salt Reactor was developed for Monte Carlo NParticle Transport [1] computational code analysis. In the course of work, two main tasks were fulfilled, which are simulation of target material behavior as a neutron convertor (producer) under 800MeV energy proton beam and criticality calculation of the designed reactor. As a result of analysis through the MCNP software, neutron flux, as well as the value of 𝑘𝑒𝑓𝑓 multiplication factor of Molten Salt Reactor for a number of different molten salts compositions assessed.
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Subchannel analysis of VVER-100 reactor core
Bednář, Michal ; Petrosyan, Taron (referee) ; Katovský, Karel (advisor)
This master’s thesis deals with boiling crisis and with departure from nucleate boiling ratio. This thesis explains terms like the boiling crisis in nuclear reactors and the thesis deals with individual parameters of the reactor core, which have an impact on departure from nucleate boiling ratio. After that, the thesis deals with subchannel analysis and describes basic mathematical and physical models of the chosen subchannel program. The thesis then processes, with the ALTHAMC12 subchannel program, the chosen parameters and their impact on departure from nucleate boiling ratio. The conclusion of the diploma thesis deals with the evaluation of the best and worst calculated combination.
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Analysis Of Passive Heat Removal Systém Trough Steam Generator By Ansoft Fluent
Petrosyan, Taron
This paper presents the simulation of the condensation of water vapor in one tube of the heat exchanger in the Passive Heat Removal System, which is a protective safety system of the Nuclear Power Plant. The simulation accounts for the turbulent flow of the gas along the tube with an assumption of constant wall temperature. The results from the CFD (computational fluid dynamics) simulations are compared with the experimental results from the literature for the condensation of water vapor and in general, agree well.
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Analysis Of Passive Heat Removal System
Through Steam Generator
Petrosyan, Taron
In the current study, the model of Passive Heat Removal System (PHRS) through Steam Generator (SG) was developed for computational fluid dynamics (CFD) analysis. During work there was done three main tasks, which are creating geometrical form of PHRS, meshing of model to achieve a better analysis of thermal-hydraulic phenomena and creating domains for simulation steam condensation in PHRS SG heat exchanger tubes. Analysis through the "ANSYS CFX" software, with two different cases investigated at the steam inlet velocity of 1 m/s and 3 m/s. A thorough description of the steam condensation process in the passive cooling system obtained as a result of the analysis. The rate of the steam condensation in heat exchanger pipeline was assessed.
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