Neutronic investigation of the application of certain plutonium-mixed fluids in a fusion–fission hybrid reactor

2021

Front. Energy Res.

In this study, a Boiling Water Reactor (BWR) design was made using the Monte Carlo (MCNPX) method. The reactor core in the designed BWR system was divided into an 8 × 8 square lattice with a constant pitch of 30.48 cm. In this study, americium (Am), which is found in the minor actinidine (MA) of spent nuclear fuel known as nuclear waste from existing reactors, was used as fuel with the addition of oxygen and fluorine. In this study, AmO2 and AmF3 fuels at the rate of 0.02–0.1% were used as Americium Mixed Fuels, and Zircaloy-2 (Zr-2), SiC, and VC were used as clad. Neutronic calculations for certain Americium Mixed Fuels and clads were compared in the designed BWR system. In the BWR system designed in the study; keff, neutron flux, fission energy, heating, and depleted Am were calculated. The three-dimensional (3-D) modeling of the designed BWR system was performed by using MCNPX-2.7.0 Monte Carlo method and the ENDF/B-VII.0 nuclear data library.

Section: Resultsmentioning

confidence: 99%

Neutronic Calculations for Certain Americium Mixed Fuels and Clads in a Boiling Water Reactor

2021

Front. Energy Res.

“…Bertini, ISABEL, and INCL4 are INC models, which can be coupled with ABLA and Dresner evaporation–fission codes. CEM2k is a cascade-preequilibrium-evaporation model 42 43 . The three-dimensional (3-D) modelling of the reactor core and fuel assembly into the designed BWR system was performed by using MCNPX-2.7.0 Monte Carlo method and the ENDF/B-VII.0 nuclear data library.…”

Section: Methodsmentioning

confidence: 99%

“…Fission energy is produced by fission reactions. The fission energy released consists of various energy modes, such as kinetic energy from fission products and fission neutrons, fast gamma rays and energy from subsequent neutron capture 43 , 48 . Fission energy was calculated using F7 tally.…”

Section: Neutron Fluxmentioning

confidence: 99%

The effect of different fuels and clads on neutronic calculations in a boiling water reactor using the Monte Carlo method

Inal

2020

Sci Rep

In this study, a Boiling Water Reactor (BWR) modeling was done for the reactor core divided into square lattice 8 × 8 type using the Monte Carlo Method. Each of the square lattices in the reactor core was divided into small square lattices 7 × 7 type in groups of four. In the BWR designed in this study, modeling was made on fuel assemblies at pin-by-pin level by using neptunium mixed fuels as fuel rod, Zr-2 and SiC as fuel cladding, H2O as coolant. In fuel rods were used NpO2 and NpF4 fuels at the rate of 0.2%-1% as neptunium mixed fuels. In this study, the effect on the neutronic calculations as keff, neutron flux, fission energy, heating of NpO2 and NpF4 fuels in 0.2%-1% rates, and Zr-2 and SiC clads were investigated in the designed BWR system. The three-dimensional (3-D) modelling of the reactor core and fuel assembly into the designed BWR system was performed by using MCNPX-2.7.0 Monte Carlo method and the ENDF/B-VII.0 nuclear data library.

“…Bertini ve ISABEL, INCL4 paketleri Dresner ve ABLA buharlaşma fisyon kodlarıyla birleştirilebilen INC modelleridir. CEM2k ise ön denge buharlaşma adım modelidir [22,23]. Bu çalışmada; reaktör koru ve yakıt grubu geometrisinin BWR sistemindeki üç boyutlu modellemesi ve Boltzmann denkleminin (Denklem 1, Denklem 2) çözülmesi için MCNPX-2.7.0 Monte Carlo yöntemi ve ENDF/B-VIII.0 nükleer veri kütüphanesi kullanıldı.…”

Section: Reaktör Kor Geometrisiunclassified

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

Süleyman Demirel Üniversitesi Fen Edebiyat Fakültesi Fen Dergisi

2020

Özet: 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.