N. Abdullah - Profile on Academia.edu (original) (raw)

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Papers by N. Abdullah

Research paper thumbnail of Cement-Boron Carbide Concrete as Radiation Shielding Material

Boron carbide (B 4 C) is a ceramic material which is effective to absorb thermal neutron due to w... more Boron carbide (B 4 C) is a ceramic material which is effective to absorb thermal neutron due to wide neutron absorption cross section. In this work, B 4 C is added into concrete as fine aggregates to test the attenuation properties by getting the attenuation coefficient of the concrete/B 4 C. The samples of concrete/B 4 C were exposing to the thermal neutron radiation source (241-Americium-Berylium) at the dos rate of 29.08 mR/h. The result show that the attenuation coefficient of the sample with 20wt% B 4 C is 0.299cm -1 and the sample without B 4 C is 0.238cm -1 and hence, concrete/B 4 C is suitable as a shield for thermal neutron radiation. ABSTRAK Boron karbida adalah bahan seramik yang berkesan untuk menyerap neutron terma kerana ia mempunyai keratan rentas penyerapan neutron yang luas. Dalam kajian ini, B 4 C ditambah dalam konkret dalam bentuk agregat halus bagi menguji sifat pelemahan menerusi penilaian pekali pelemahan konkret/B4C. Sampel konkret telah didedahkan kepada sum...

Research paper thumbnail of Cement-Boron Carbide Concrete as Radiation Shielding Material

Boron carbide (B 4 C) is a ceramic material which is effective to absorb thermal neutron due to w... more Boron carbide (B 4 C) is a ceramic material which is effective to absorb thermal neutron due to wide neutron absorption cross section. In this work, B 4 C is added into concrete as fine aggregates to test the attenuation properties by getting the attenuation coefficient of the concrete/B 4 C. The samples of concrete/B 4 C were exposing to the thermal neutron radiation source (241-Americium-Berylium) at the dos rate of 29.08 mR/h. The result show that the attenuation coefficient of the sample with 20wt% B 4 C is 0.299cm -1 and the sample without B 4 C is 0.238cm -1 and hence, concrete/B 4 C is suitable as a shield for thermal neutron radiation. ABSTRAK Boron karbida adalah bahan seramik yang berkesan untuk menyerap neutron terma kerana ia mempunyai keratan rentas penyerapan neutron yang luas. Dalam kajian ini, B 4 C ditambah dalam konkret dalam bentuk agregat halus bagi menguji sifat pelemahan menerusi penilaian pekali pelemahan konkret/B4C. Sampel konkret telah didedahkan kepada sum...

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