On the use of green concrete composite as a nuclear radiation shielding material

2021 ◽  
Vol 136 ◽  
pp. 103730
Author(s):  
Sukhpal Singh ◽  
Kanwaldeep Singh
Keyword(s):  
Radiation Shielding ◽  
Nuclear Radiation ◽  
Green Concrete ◽  
Shielding Material

scholarly journals Review on the Change Law of the Properties and Performance of Polymer-Matrix Nuclear Radiation Shielding Materials Under the Coupling of Nuclear Radiation and Thermal Effects

2021 ◽  
Vol 9 ◽  
Author(s):  
Guang Hu ◽  
Weiqiang Sun ◽  
Yihong Yan ◽  
Rongjun Wu ◽  
Hu Xu
Keyword(s):  
Mechanical Properties ◽  
Polymer Matrix ◽  
Thermal Effects ◽  
Nuclear Power ◽  
Power Plants ◽  
Radiation Shielding ◽  
Nuclear Radiation ◽  
And Performance ◽  
Shielding Material

The polymer-matrix nuclear radiation shielding material is an important component of nuclear power plants. However, its mechanical properties and shielding performance gradually deteriorate due to the long-term synergy of nuclear radiation and thermal effects, which brings hidden dangers to the safe operation of the device. Based on this problem, this article makes a comprehensive review. First, the degradation of mechanical properties and shielding performance of polymer-matrix nuclear radiation materials in service is briefly described. Then, the research methods adopted by scholars to study the change law of properties and performance are introduced, and the main existing difficulties encountered by the study are summarized. Finally, the physical mechanism of the change of material properties is explained in detail, and a reference approach to solving the problem is proposed.

Optimizing Gamma-Ray Shielding Material by Using Genetic Algorithm and MCNP Code

2010 ◽  
Author(s):  
Sahar Ashayer ◽  
Mansur Asgari ◽  
Hossein Afarideh
Keyword(s):  
Genetic Algorithm ◽  
Gamma Ray ◽  
Radiation Shielding ◽  
Nuclear Radiation ◽  
Mcnp Code ◽  
Biological Damage ◽  
Manned Spacecraft ◽  
Multi Objective Genetic Algorithm ◽  
Low Weight ◽  
Shielding Material

Radiation shielding material investigations is an important subject which relates to human safety, for those engaging in medical radiation, radiology, and facilities related with nuclear radiation, manned spacecraft and so on. Therefore necessity of finding effective shielding materials which have low weight, and cost, and have stability against radiation, with high temperature resistant, and no biological damage,… is obvious. On the other hand, because of the multi-variability of the problem, it is experimentally difficult to determine the optimum values of the concerned variables. For this reason, simulation for discovering optimized shielding material is important. Parameters such as attenuation, thickness, and cost of gamma radiation shielding materials were optimized by using genetic algorithm combined with MCNP code. Multi objective genetic algorithm (GA) is one of the scientific solutions for this problem.

scholarly journals The effect of boron and titanium addition on the behavior of steel alloys of base composition AISI304 as a nuclear radiation shielding material

2019 ◽  
Vol 0 (0) ◽  
pp. 0-0
Author(s):  
Shaimaa Hafez ◽  
Samir El-Kameesy ◽  
Mamdouh Eissa ◽  
Raed Elshazly ◽  
Mohamed ELFAWKHRY ◽  
...  
Keyword(s):  
Base Composition ◽  
Radiation Shielding ◽  
Nuclear Radiation ◽  
Titanium Addition ◽  
Steel Alloys ◽  
Shielding Material

scholarly journals Designing and preparing for a 288○C heat resistant and inhibition of gas production resin matrix nuclear radiation shielding material

AIP Advances ◽  
2019 ◽  
Vol 9 (12) ◽  
pp. 125044
Author(s):  
Guang Hu ◽  
Huasi Hu ◽  
Weiqiang Sun ◽  
Yihong Yan ◽  
Mingfei Yan
Keyword(s):  
Gas Production ◽  
Radiation Shielding ◽  
Nuclear Radiation ◽  
Resin Matrix ◽  
Heat Resistant ◽  
Shielding Material

Comparison of Lead, Copper and Aluminium as Gamma Radiation Shielding Material through Experimental Measurements and Simulation Using MCNP Version 4c

2018 ◽  
Vol 9 (08) ◽  
pp. 20193-20206 ◽  
Author(s):  
Md. Akhlak Bin Aziz ◽  
Md. Faisal Rahman ◽  
Md. Mahidul Haque Prodhan
Keyword(s):  
Gamma Radiation ◽  
Sodium Iodide ◽  
Experimental Approach ◽  
Radiation Shielding ◽  
Test Material ◽  
Simulation Techniques ◽  
Radiation Sources ◽  
Simulation Monte Carlo ◽  
Shielding Material ◽  
Code Version

The paper compares  Lead, Copper and Aluminium as gamma radiation shielding material using both experimental and simulation techniques. Cs- 137 (662KeV), Na-22 (511KeV) and Na- 22(1274KeV) were used as gamma radiation sources and a sodium iodide (NaI) detector was used to detect the radiation. Variations were noted for detected gamma count rates by changing shielding material thickness. In the experimental approach, thickness was varied by placing sheets of a particular test material one by one. For simulation, Monte Carlo n- Particle (MCNP) code version 4c was used and the geometry of the whole experimental setup was plotted in it. The results were then compared for each test material and it was found that lead is the best shielding material for gamma radiation followed by copper and aluminium.

scholarly journals In Silicon Monte Carlo Simulation Trials for Investigation of V2O5 Reinforcement Effect on Ternary Zinc Borate Glasses: Nuclear Radiation Shielding Dynamics

Materials ◽  
2021 ◽  
Vol 14 (5) ◽  
pp. 1158
Author(s):  
Huseyin O. Tekin ◽  
Shams A. M. Issa ◽  
Gokhan Kilic ◽  
Hesham M. H. Zakaly ◽  
Mohamed M. Abuzaid ◽  
...  
Keyword(s):  
Effective Atomic Number ◽  
Mean Free Path ◽  
Radiation Shielding ◽  
Nuclear Radiation ◽  
Zinc Borate ◽  
Linear Attenuation Coefficient ◽  
Buildup Factor ◽  
Glass Composites ◽  
Mcnpx Code ◽  
Negative Effect

In the current study, promising glass composites based on vanadium pentoxide (V2O5)-doped zinc borate (ZnB) were investigated in terms of their nuclear-radiation-shielding dynamics. The mass and linear attenuation coefficient, half-value layer, mean free path, tenth-value layer, effective atomic number, exposure-buildup factor, and energy-absorption-buildup factor were deeply simulated by using MCNPX code, Phy-X PSD code, and WinXcom to study the validation of ZBV1, ZBV2, ZBV3, and ZBV4 based on (100−x)(0.6ZnO-0.4B2O3)(x)(V2O5) (x = 1, 2, 3, 4 mol%) samples against ionizing radiation. The results showed that attenuation competencies of the studied glasses slightly changed while increasing the V2O5 content from 1 mol% to 4 mol%. The domination of ZnO concentration in the composition compared to B2O3 makes ZnO substitution with V2O5 more dominant, leading to a decrease in density. Since density has a significant role in the attenuation of gamma rays, a negative effect was observed. It can be concluded that the aforementioned substitution can negatively affect the shielding competencies of studied glasses.

scholarly journals Analysis of Shielding Performance of Radiation-Shielding Materials According to Particle Size and Clustering Effects

2021 ◽  
Vol 11 (9) ◽  
pp. 4010
Author(s):  
Seon-Chil Kim
Keyword(s):  
Particle Size ◽  
Polymer Material ◽  
Energy Region ◽  
High Energy ◽  
Radiation Shielding ◽  
High Energy Region ◽  
Particle Structure ◽  
Effect Of Particle Size ◽  
Extensive Body ◽  
Shielding Material

In the field of medical radiation shielding, there is an extensive body of research on process technologies for ecofriendly shielding materials that could replace lead. In particular, the particle size and arrangement of the shielding material when blended with a polymer material affect shielding performance. In this study, we observed how the particle size of the shielding material affects shielding performance. Performance and particle structure were observed for every shielding sheet, which were fabricated by mixing microparticles and nanoparticles with a polymer material using the same process. We observed that the smaller the particle size was, the higher both the clustering and shielding effects in the high-energy region. Thus, shielding performance can be improved. In the low-dose region, the effect of particle size on shielding performance was insignificant. Moreover, the shielding sheet in which nanoparticles and microsized particles were mixed showed similar performance to that of the shielding sheet containing only microsized particles. Findings indicate that, when fabricating a shielding sheet using a polymer material, the smaller the particles in the high-energy region are, the better the shielding performance is. However, in the low-energy region, the effect of the particles is insignificant.

Incorporation of copper slag in cement brick production as a radiation shielding material

2021 ◽  
pp. 109851
Author(s):  
Sungwon Sim ◽  
Dongho Jeon ◽  
Do Hoon Kim ◽  
Woo sung Yum ◽  
Seyoon Yoon ◽  
...  
Keyword(s):  
Copper Slag ◽  
Radiation Shielding ◽  
Shielding Material
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