Calculation of Shielding Parameters of Fast Neutrons for Some Composite Materials

Mkhaiber, Ahmed Fadhil; Dawood, Salwah Kareem

doi:10.23851/mjs.v30i1.520

Cited by 4 publications

(3 citation statements)

References 3 publications

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“…This build-up is due to the inelastic scattering interaction between neutrons and the iron atomic nucleus, which excites the atomic nucleus after the reaction. The atomic nucleus returns to the ground-level state by emitting photons [47]. The probability of inelastic scattering is high when the neutrons collide with dense material or heavy atomic nuclei.…”

Section: Effective Dose and Ambient Dose H*(10) Equivalent Analysismentioning

confidence: 99%

Combined Method of Bulk Material Shielding Evaluation for 200 Mev High Energy Neutron Source Using Phits Modelling and Partial Density

Aliyah

Rahman

Radzi

et al. 2023

SPEKTRA

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Neutron encounters difficulties in shielding protection. Thus, many researchers have performed simulation and experimental research on neutron shielding materials. The characteristic of materials is highly dependent on neutron energy. The evaluation of neutron shielding for various materials, such as iron, concrete, aluminum, and borated polyethylene (BPE), was conducted in this paper through simulation using a Monte Carlo code of PHITS 3.27 and calculation via partial density method. A mono-energetic neutron source with an energy of 200 MeV is emitted perpendicular to the shielding material with a thickness of 105 cm. The parameters measured in this analysis include flux, fast neutron removal cross-section, neutron depth dose, ambient dose H*(10) equivalent, and neutron dose reduction factor (RF). Results show that iron is a good material against high-energy neutron and secondary photon radiation at the energy range with the highest removal cross-section and the lowest RF value (0.39), followed by concrete, BPE, and aluminum. The integrated fluence and effective dose profiles were consistent with previous results in the literature. Benchmarking calculation of neutron dose RF was conducted with other publications and was in good agreement within the value range.

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Section: Effective Dose and Ambient Dose H*(10) Equivalent Analysismentioning

confidence: 99%

Combined Method of Bulk Material Shielding Evaluation for 200 Mev High Energy Neutron Source Using Phits Modelling and Partial Density

Aliyah

Rahman

Radzi

et al. 2023

SPEKTRA

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show abstract

“…One of the protection methods against ionizing radiation is shielding which is complex especially in case of neutron because neutrons interact with matter only through nuclei, so they do not moderate easily through the exposed matter, and can travel a large distance through most materials without scattering or absorbing. This means that the neutrons have a high ability to penetrate such materials, which makes them dangerous both in terms of material and radiation [2].…”

Section: Introductionmentioning

confidence: 99%

Radiation Shielding Against Neutron Using Different Fillers: Review Study

Mohamedy¹

2023

Arab Journal of Nuclear Sciences and Applications

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Radiation Shielding Concrete is mixture of cement, water, and heavy weight Aggregates (Fillers) commonly used as shielding against radiation as neutrons that emitted in different facilities as the medical units, particle accelerators. Neutrons causing extra doses to the patient and the occupational workers which is the main issue to grantee radiation safety. Various special Concretes containing fillers have been produced and used for enhancing the radiation shielding characteristics of the ordinary concrete. Only light elements as boron and hydrogen acts as moderate for neutrons that can absorb them. Therefore, for neutrons radiation shielding; concrete must contain light elements beside the heavy elements. Many softwires were employed to examine the effectiveness of the concretes as a radiation shielding materials, also Monte Carlo (MC) simulation program that simulates the transmission and interaction of radiation with different matters. Those software and simulation programs can be used in different fields such as, radiation physics, medicine, and researches. In this paper different fillers added to the ordinary concrete and different measuring methods will be reviewed.

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“…This indicates that neutrons have a high penetrability ability, making them hazardous in material and radiation considerations. The removal cross-section, mean free path, and half-value thickness, are used to characterize neutron interactions with materials [4].…”

Section: Introductionmentioning

confidence: 99%

Investigation of Shielding for Fast Neutrons Using Polymer Composites with Pb Reinforcement

Hmood,

Hussain

2023

Iraqi Journal of Science

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Manufacturing high-efficiency polymeric materials to moderate fast neutrons by converting them into slow or thermal neutrons. These materials absorb thermal neutrons as well as gamma rays associated with neutrons. Materials of small mass number are used to slow down fast neutrons because neutrons have a high cross-section when they interact with these materials. Materials of high mass number absorb gamma rays. Polyurethane and epoxy were mixed in various ratios to create a blend to serve as neutrons shield, lead (Pb) was then added to the blend at weight percentages of 20%, 30%, 40%, 50%, and 70% to produce a polymer composite. Polymeric materials reinforced with lead in various ratios were tested to select the best composite. The Polymeric samples were placed between the neutron source and the detector, and changing their thickness from 1 cm to 10 cm in increments of 1 cm. The neutron count rate for five readings was recorded, and the average was taken. As a result, the relationship between count rate and sample thickness was plotted, the half-value thickness of the shield was determined, the relationship between the logarithm ( ) and the thickness was drawn, the removal cross-section ( ) was determined, as well as, the mean free path of the fast neutron, and these were compared for each sample. This work concluded that the sample containing 20% lead with a thickness of 10 cm and a diameter of 4 cm was the best shielding for absorbing fast neutrons. The removal cross-section (∑R) was analyzed, and the value of half-thickness of the shield, as well as the mean free path of the fast neutron, were determined and compared for each sample. During the research, it was revealed that a sample containing 20% lead was the best shielding for absorbing fast neutrons.

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Calculation of Shielding Parameters of Fast Neutrons for Some Composite Materials

Cited by 4 publications

References 3 publications

Combined Method of Bulk Material Shielding Evaluation for 200 Mev High Energy Neutron Source Using Phits Modelling and Partial Density

Combined Method of Bulk Material Shielding Evaluation for 200 Mev High Energy Neutron Source Using Phits Modelling and Partial Density

Radiation Shielding Against Neutron Using Different Fillers: Review Study

Investigation of Shielding for Fast Neutrons Using Polymer Composites with Pb Reinforcement

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