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

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Günay M., Sanchez Espinoza V., Travleev A.

Acta Physica Polonica A

2015

vol. 128

issue 2B

B-110-B-112

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.

Radiation Protection by the Barite Coated Fabrics via Image Processing Methodology

100%

Akarslan F., Molla T., Akkurt İ., Kilinçarslan Ş., Üncü I.

vol. 125

issue 2

316-318

According to developing technology and conditions of modern life, use of radiation is rapidly increased. Unwittingly, our organs and tissues are exposed to radiation continuously. In order to avoid exposure to this radiation, some studies were carried out on protective clothing. In this study, radiation keeping properties of the fabrics coated with barite are examined. Radiation keeping properties were also determined by the method of image processing. After the experiments, it is determined that barite-coated fabrics absorb radiation better than normal fabrics.

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2 Acta Physica Polonica A

1 2015

1 2014

1 Akarslan F.

1 Akkurt İ.

1 Günay M.

1 Kilinçarslan Ş.

1 Molla T.

1 Sanchez Espinoza V.

1 Travleev A.

1 Üncü I.

Search results

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

Radiation Protection by the Barite Coated Fabrics via Image Processing Methodology