Measurement and Monte Carlo simulation of γ-ray dose rate in high-exposure building materials  被引量:1

Measurement and Monte Carlo simulation of γ-ray dose rate in high-exposure building materials

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作  者:A. Abbasi M. Hassanzadeh 

机构地区:[1]Reactor Research School, Nuclear Science and Technology Institute (NSTRI), P.O. Box 141551339, Tehran, Iran [2]University of Kyrenia, Kyrenia, North Cyprus, Mersin 10,Turkey

出  处:《Nuclear Science and Techniques》2017年第2期30-34,共5页核技术(英文)

摘  要:Natural radioactivity radionuclides in building materials, such as^(226)Ra,^(232)Th and^(40)K, cause indoor exposure due to their gamma-rays. In this research, in a standard dwelling room(5.0 m 9 4.0 m 9 2.8 m), with the floor covered by various granite stones, was set up to simulate the dose rates from the radionuclides using MCNP4 C code. Using samples of granite building products in Iran, activities of the^(226)Ra,^(232)Th and^(40)K were measured at 3.8–94.2, 6.5–172.2 and 556.9–1529.2 Bq kg^(-1),respectively. The simulated dose rates were26.31–184.36 n Gy h^(-1), while the measured dose rates were 27.70–204.17 n Gy h^(-1). With the results in good agreement, the simulation is suitable for any kind of dwelling places.Natural radioactivity radionuclides in building materials, such as <sup>226</sup>Ra, <sup>232</sup>Th and <sup>40</sup>K, cause indoor exposure due to their gamma-rays. In this research, in a standard dwelling room (5.0 m × 4.0 m × 2.8 m), with the floor covered by various granite stones, was set up to simulate the dose rates from the radionuclides using MCNP4C code. Using samples of granite building products in Iran, activities of the <sup>226</sup>Ra, <sup>232</sup>Th and <sup>40</sup>K were measured at 3.8-94.2, 6.5-172.2 and 556.9-1529.2 Bq kg<sup>−1</sup>, respectively. The simulated dose rates were 26.31-184.36 nGy h<sup>−1</sup>, while the measured dose rates were 27.70-204.17 nGy h<sup>−1</sup>. With the results in good agreement, the simulation is suitable for any kind of dwelling places.

关 键 词:RADIOACTIVITY Building materials Absorbed DOSE Experimental MCNP4C 

分 类 号:TL81[核科学技术—核技术及应用]

 

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