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- 저자 : Afshin Hedayat (검색결과 2 건)
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Afshin Hedayat 한국원자력학회 2017 Nuclear Engineering and Technology Vol.49 No.5
In this paper, a complete station blackout (SBO) or complete loss of electrical power supplies is simulatedand analyzed in a downward cooling 5-MW pool-type Material Testing Reactor (MTR). The scenario istraced in the absence of active cooling systems and operators. The code nodalization is successfullybenchmarked against experimental data of the reactor's operating parameters. The passive heat removalsystem includes downward water cooling after pump breakdown by the force of gravity (where thecoolant streams down to the unfilled portion of the holdup tank), safety flapper opening, flow reversalfrom a downward to an upward cooling direction, and then the upward free convection heat removalthroughout the flapper safety valve, lower plenum, and fuel assemblies. Both short-term and long-termnatural core cooling conditions are simulated and investigated using the RELAP5 code. Short-term analysesfocus on the safety flapper valve operation and flow reversal mode. Long-term analyses includesimulation of both complete SBO and long-term operation of the free convection mode. Results arepromising for pool-type MTRs because this allows operators to investigate RELAP code abilities for MTRthermalehydraulic simulations without any oscillation; moreover, the Tehran Research Reactor isconservatively safe against the complete SBO and long-term free convection operation.
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Ali Farsoon Pilehvar,Mohammad Hossein Esteki,Afshin Hedayat,GHOLAM REZA ANSARIFAR 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.5
Self-pressurization analysis of the natural circulation integral nuclear reactor through a new dynamicmodel is studied. Unlike conventional pressurized water reactors, this reactor type controls the systempressure using saturated coolant water in the steam dome at the top of the pressure vessel. Selfpressurizationmodel is developed based on conservation of mass, volume, and energy by predictingthe condensation that occurs in the steam dome and the flashing inside the chimney using the partialdifferential equation. A simple but functional model is adopted for the steam generator. The obtainedresults indicate that the variable measurement is consistent with design data and that this new model isable to predict the dynamics of the reactor in different situations. It is revealed that flashing andcondensation power are in direct relation with the stability of the system pressure, without whichpressure convergence cannot be established.
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