عنوان :
محاسبات نوتروني براي انبارش سوخت هاي رآكتورهاي هسته اي به روش شبيه سازي با استفاده از كد MCNP
مقطع تحصيلي :
كارشناسي ارشد
محل تحصيل :
اصفهان : دانشگاه صنعتي اصفهان
صفحه شمار :
سيزده، 63ص.: مصور، جدول، نمودار
استاد راهنما :
احمد شيراني
استاد مشاور :
هادي شامرادي فر
توصيفگر ها :
سوخت هسته اي , شرايط بحرانيت , واكنش زنجيره اي , ايمني هسته اي , كد MCNP
استاد داور :
محمدحسن علامت ساز، مريم حسنوند
تاريخ ورود اطلاعات :
1400/03/04
تاريخ ويرايش اطلاعات :
1400/03/04
چكيده انگليسي :
چك دة انگل سي Neutronic Calculations for Storage of Nuclear Reactor Fuels by Simulation Method Using MCNP Code Ali Ahmadi Ali ahmadi96@ph iut ac ir 13 March 2021 Department Of Physics Isfahan University of Technology Isfahan 84156 83111 IranDegree M Sc Language FarsiAhmad Shirani Shirani@cc iut ac ir AbstractNuclear fuel cycle facilities are responsible for supplying fuel to nuclear reactors Due to the useof various compounds of uranium and toxic substances in nuclear fuel cycle facilities it isnecessary to consider all safety considerations at the design stage In general safety objectivesshould cover general safety objectives radiation protection and technical safety and nuclearsafeguards fuel cycle sub facilities Nuclear safety can be ensured by limiting at least one of thecritical determinants This is done in a way that makes it physically impossible to create a self sustaining chain reaction Controlling the mass of fissile isotopes controlling the geometric shapeof nuclear storage tanks and controlling the arrangement of nuclear storage tanks are basic controlmethods In this dissertation the unused nuclear fuel storage depot with different layouts wassimulated in 3 7 5 and 20 enrichment using the MCNPX calculation code Due to theimportance of nuclear safety and the closeness of the calculations to reality the dimensions of thetanks have been simulated exactly based on the dimensions of the tanks used in the Atomic EnergyOrganization of Isfahan Also 4 common types of reactor fuels are UO2 U3O8 ADU and AUCwere used separately The storage space of the simulated nuclear fuel consists of 45 steel fuelcylinders in three floors and with our different distances between the cylinders and thecalculations of the effective multiplication factor the flux from the cylinders containing the fueland the following the total dose of neutrons and gamma was performed According to the obtainedresults the optimal arrangement of fuel cylinders in terms of criticality and amount of radiationwas introduced The results of these calculations can be used to design different reservoir layouts and preventnuclear accidents Keywords Nuclear Fuel Critical Conditions Chain Reaction Nuclear Safety MCNP Code
استاد راهنما :
احمد شيراني
استاد مشاور :
هادي شامرادي فر
استاد داور :
محمدحسن علامت ساز، مريم حسنوند
