Gamma-ray absorption using rubber—lead mixtures as radiation protection shields

Mheemeed, Ahmed K.; Hasan, Hana Ihsan; Al-jomaily, Firas Mohammed Ali

doi:10.1007/s10967-011-1556-2

Cited by 29 publications

(13 citation statements)

References 7 publications

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“…Polymers are one of the favorite matrix materials used for IEMR shielding composites because of their light weight. Polymer-bismuth (Plionis et al, 2009), lead-natural rubber (Gwaily and Madani, 2002;Mheemeed et al, 2011) and lead-unsaturated polyester composites are some of studied polymer based composites for radiation shielding.…”

mentioning

confidence: 99%

Preparation and characterization of a novel ionizing electromagnetic radiation shielding material: Hematite filled polyester based composites

Belgin

Ayçık

Kalemtaş

et al. 2015

Radiation Physics and Chemistry

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mentioning

confidence: 99%

Preparation and characterization of a novel ionizing electromagnetic radiation shielding material: Hematite filled polyester based composites

Belgin

Ayçık

Kalemtaş

et al. 2015

Radiation Physics and Chemistry

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“…The results show in Tables-(3, 4) are displayed in Figures-(3, 4, 5 and 6) it can be seen the linear attenuation increased with cement -waste thickness. The plots in Figures-(5, 6) show the responding relation between the final dose rate of cemented waste bulk and the depth shield along the R axis of the sample or 662Kev gamma energy [6,7]. The dose rate of the 137 Cscontained by cemented waste and carbon steel container specimen was dropped to very low values which are within waste acceptance criteria (WAC) [8].…”

Section: (2) [5]mentioning

confidence: 99%

Hypothetical Method for Gamma Dose Rate Assessment to Conditioned Radioactive waste Container

Saad

Beden

Halboot

et al. 2018

ijs

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Metallic solid radioactive waste class low level -short lived Radioactive Waste (LL-SL RW) is the main type of radioactive waste generated from decommissioning operations. Transport, storage and disposal regulations require for gamma emitting radioactive waste (mainly by 137 Csisotope), that the dose rate in the proximity of the container should stand below a certain threshold. Also, the conditioning technique (using cementation technique) based on certain matrix with specific ratios should be able to attenuate the gamma radiation activity to the minimum level or to acceptable dosage rate at distance of 1m from the container. In this paper ,in absence of suitable labs for waste package assessment ,hypothetical method present to assess dose rate in safe way, assumption based on metallic waste pieces contaminated with ( 137 Cs), were conditioned with cement matrix and contained in carbon steel drum volume 220 liter ,60cm diameter then dose rate measurement applied in vicinity of the container. Instead of real contaminated metallic waste, ( 137 Cs,D∘=20mR/hr) gamma radioactive point source was positioned in different places in front of cross section of the cemented free metallic waste and gamma dose rates were measured on the outer side of the drum sample using NaI dose meter device. The readings showed good attenuation of gamma radiation activity (low dose rates), efficiency of the cement matrix to decrease the dose rate of ( Iraqi Journal of Science, 2018, Vol. 59, No.1C, pp: 476-

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“…B: Accumulation factor To get rid of the accumulation factor and to achieve exponential attenuation law in equation (1), a narrow beam of gamma rays should be used by using the shooting [12]. The attenuation coefficient (μ) is associated with the number of atoms in 1 cm 3 of absorbed matter and whole cross-section (E) σ of the interaction of photons with matter.…”

Section: Theoretical Partmentioning

confidence: 99%

Study the Attenuation Coefficient of Granite to Use It as Shields against Gamma Ray

Najam¹,

Hashim²,

Ahmed³

et al. 2016

Detection

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The present work investigates the linear and mass attenuation coefficients for gamma rays practically and theoretically by using spectroscopy gamma ray (UCS-20) and program (XCOM)) for various types of common use granite, and compares them with the lead because of its high blocking ability for this type of radiation. This paper concluded through linear and mass attenuation coefficients measurements that these coefficients decrease with increasing incident photons energy. Measurements also showed that the linear attenuation coefficients appropriate linearly with density while mass attenuation coefficients do not get affected.

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Gamma-ray absorption using rubber—lead mixtures as radiation protection shields

Cited by 29 publications

References 7 publications

Preparation and characterization of a novel ionizing electromagnetic radiation shielding material: Hematite filled polyester based composites

Preparation and characterization of a novel ionizing electromagnetic radiation shielding material: Hematite filled polyester based composites

Hypothetical Method for Gamma Dose Rate Assessment to Conditioned Radioactive waste Container

Study the Attenuation Coefficient of Granite to Use It as Shields against Gamma Ray

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