Investigation of Some Neutronic Values for Np and Am Fuel Rods in a Boiling Water Reactor Modeling

Year 2020, , 140 - 147, 31.05.2020

Mehtap Düz

https://doi.org/10.29233/sdufeffd.705690

Abstract

In this study, some neutronic values were investigated in modeling three-dimensional boiling water reactor (BWR) using Monte Carlo method. In BWR modeling, the reactor core was designed by dividing it into 8x8 type square lattices and each square lattice in itself into 7x7 type small square lattices. In this study, small square lattices of 7x7 type were created by using Neptunium (Np) and Americium (Am) minor actinides at the rate of 0.02-0.1% as fuel rod, Zirkolay-2 (Zr-2) as fuel clad, water as coolant. B4C control rods were placed in 8x8 type square lattices in the cruciform area. In BWR modeling, keff, fission energy and heat deposition rate neutronic values were calculated for Np and Am fuel rods at the rate of 0.02-0.1% and Zr-2 fuel clad. Three-dimensional modeling of the BWR system was designed using MCNPX-2.7.0 Monte Carlo method and ENDF/B-VIII.0 nuclear data library.

Keywords

BWR, Neutronic values, MCNPX-2.7.0

Bir Kaynar Su Reaktör Modellemesinde Np ve Am Yakıt Çubukları için Bazı Nötronik Değerlerin İncelenmesi

Abstract

Bu çalışmada Monte Carlo metodu kullanılarak üç boyutlu kaynar su reaktör (BWR) modellemesinde bazı nötronik değerler incelendi. BWR modellemesinde reaktör koru 8x8 tipinde kare kafeslere ve her kare kafes kendi içinde 7x7 tipinde küçük kare kafeslere bölünerek tasarlandı. Bu çalışmada, yakıt çubuğu olarak % 0,02-0,1 oranlarında Neptünyum (Np) ve Amerisyum (Am) minör aktinitleri, yakıt zırhı olarak Zirkolay-2 (Zr-2), soğutucu olarak su kullanılarak 7x7 tipinde küçük kare kafesler oluşturuldu. 8x8 tipinde kare kafesler içine B4C kontrol çubukları haç şeklindeki bölgede yerleştirildi. BWR modellemesinde % 0,02-0,1 oranlarında Np ve Am yakıt çubukları ve Zr-2 yakıt zırhı için keff, fisyon enerjisi ve depolanan ısınma oranı nötronik değerleri hesaplandı. MCNPX-2.7.0 Monte Carlo metodu ve ENDF/B-VIII.0 nükleer veri kütüphanesi kullanılarak BWR sisteminin üç boyutlu modellemesi tasarlandı.

Keywords

BWR, Nötronik değerler, MCNPX-2.7.0

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