توجه: محتویات این صفحه به صورت خودکار پردازش شده و مقاله‌های نویسندگانی با تشابه اسمی، همگی در بخش یکسان نمایش داده می‌شوند.
۱Thermal–hydraulic analysis of VVER–1000 reactor during LOFA
نویسنده(ها): ، ،
اطلاعات انتشار: کنفرانس بین المللی مهندسی و علوم کاربردی، سال
تعداد صفحات: ۷
The Loss Of Flow Accident (LOFA) is one of the most important Design Basis Accidents (DBA) in the reactor analysis. A loss of coolant flowcan occur from mechanical failure or power supply which could cause a reduction in flow. This paper provides a transient thermal–hydraulicmodel of VVER–1000 reactor during LOFA by RELAP5 code. The obtained results from the RELAP5 transient analysis showed areasonable agreement with the Bushehr NPP Final Safety Analysis Reports (FSAR). Also the results show that by effective function ofprotection systems in the beginning of the accident, the reactor maintains its safety margin<\div>

۲Nanofluid application in VMHWR
نویسنده(ها): ، ،
اطلاعات انتشار: کنفرانس بین المللی مهندسی و علوم کاربردی، سال
تعداد صفحات: ۹
The main objective of this study is to predict the neutronic behavior of nanofluids as the coolant in the fuel assembly of HPLWR. The High–Performance Light Water Reactor (HPLWR) is the European version of the Supercritical–pressure Water Cooled Reactor (SCWR). Light water reactors at supercritical pressure, being currently under design, are the new generation of nuclear reactors. VMHWR is the new version of HPLWR conceptual design. In this design, the fluid passing through the moderator channels and the assembly gaps (known as a moderator) flows in channels detached from coolants. The variations of neutron cross sections, effective multiplication factor and thermal power have been investigated in different concentrations of nanoparticles in coolant and moderator channel. In this analysis, water–based nanofluids containing various volume fractions of Al2O3, TiO2, CuO and Cu nanoparticles are studied. The neutronic properties of nanofluids with optimum concentration of nanoparticles are calculated using WIMS and CITATION codes. The results show that at low concentrations (less than 1 volume percentage) alumina is the optimum nanoparticle for normal reactor operation.<\div>

۳Thermal hydraulic Analysis of VVER–1000 Condenser by RELAP5 Code
اطلاعات انتشار: دومین کنفرانس بین المللی پژوهش در علوم و تکنولوژی، سال
تعداد صفحات: ۶
From the point of view of plant availability, condenser performance is extremely important. It is even more crucial in cases of aged NPPs. Condenser performance plays a key role in nuclear power plant safety. For the analysis of a nuclear power plant, it is essential to have a reliable thermal–hydraulic model of condenser. The aim of this study is to conduct a thermal–hydraulic analysis of a Bushehr VVER–1000 reactor condenser. This paper provides a semi two dimensional thermal–hydraulic model of the condenser using the RELAP5 code. Two main advantages of the present model are the application of a valid nodalization method and a consideration of the cross–flow effects. The obtained results from the RELAP5 steady state analysis were in reasonable agreement with the Bushehr NPP Final Safety Analysis Reports (FSAR).<\div>
نمایش نتایج ۱ تا ۳ از میان ۳ نتیجه