The Effect on Neutronic Calculations of Certain Alternative Fuels in a Boiling Water Reactor by Using MCNPX Monte Carlo Method

• Authors: M. Günay , V. Sanchez Espinoza , A. Travleev
• Languages of publication: EN

Abstracts

EN

We were studying on the modeling of boiling water reactor fuel assemblies at pin-by-pin level by using Monte Carlo method. The designed boiling water reactor system is cylinder, and the radius of the cylinder is 228 cm. The total active core height is 315.79 cm. The reactor core was divided into the square lattice 7 × 7 type with a constant pitch of 30 cm. The core was surrounded with the reflector. The reflector was surrounded by SS316LN ferritic steel with width of 3 cm. The mixtures 0.2-1% PuF₄ and PuO₂ were used as fuel. In this study, the effect on the neutronic calculations of PuF₄ and PuO₂ fuels was investigated in the designed boiling water reactor system. There were calculated k_{eff}, heat deposition and the fission energy in the designed boiling water reactor system. The three-dimensional (3D) modelling of the reactor core and fuel assembly into the designed boiling water reactor system was performed by using MCNPX-2.7.0 Monte Carlo method and the ENDF/B nuclear data library.

Keywords

EN

28.41.-i; 28.41.Ak

Discipline

• 28.41.Ak: Theory, design, and computerized simulation
• 28.41.-i: Fission reactors(see also 89.30.Gg nuclear fission power in energy resources)

• Publisher: Institute of Physics, Polish Academy of Sciences
• Journal: Acta Physica Polonica A
• Year: 2015
• Volume: 128
• Issue: 2B
• Pages: B-110-B-112

Dates

published

2015-8

Contributors

author

M. Günay

• İnönü University, Physics Department, Malatya, Turkey

author

V. Sanchez Espinoza

• Karlsruhe Institute of Technology, Institute for Neutron Physics and Reactor Technology (INR), Karlsruhe, Germany

author

A. Travleev

• Karlsruhe Institute of Technology, Institute for Neutron Physics and Reactor Technology (INR), Karlsruhe, Germany

References

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Identifiers

DOI

10.12693/APhysPolA.128.B-110