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Li Z.,Northeastern University China | Li Z.,Liaoning key laboratory for ecologically comprehensive utilization of boron resources and materials | Xue X.,Northeastern University China | Xue X.,Liaoning key laboratory for ecologically comprehensive utilization of boron resources and materials | And 8 more authors.
Materials Science Forum | Year: 2013

Four novel boron containing ores/epoxy composites were prepared by using nature ludwigite green ore (NLGO), artificial ores including boron containing iron ore concentrate (BCIOC), boron rich slag (BRS) and boron mud (BM) as neutron absorbers, which were obtained by dressing from NLGO, blast furnace separation from BCIOC and borax production, respectively. The microstructure of the composites was investigated by X-ray diffraction (XRD), scanning electron microscope (SEM) and Fourier transform infrared spectroscopy (FT-IR). Shielding properties of the composites against thermal and Cf-252 fast neutron were measured. Factors affecting the shielding properties were investigated. Energy deposition, absorbed dose and half value layers of the composites against neutron penetration were simulated by Monte Carlo method, and a simulated function was obtained. The results showed that the composites were compact and the particles of ores were homogeneous. Ascending boron mole numbers per unit volume (nB) in the composites can obviously enhance the macroscopic absorbing cross section (Σthermal) and improve the shielding properties for thermal neutron. The relationship of Σthermaland nBfollows the equation of Σthermal=0.218+450.490nB. And the relationship of average atomic number (Z) of boron containing ores composites and the macroscopic removal cross section for fast neutron follows the equation of Σremoval=0.042exp (-Z/5.70)+0.032. Enhancement of the shielding abilities against Cf-252 fast neutron can be achieved by using the composites with low average atomic number. © (2013) Trans Tech Publications, Switzerland.


Li Z.F.,Northeastern University China | Li Z.F.,Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials | Xue X.X.,Northeastern University China | Xue X.X.,Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials | And 6 more authors.
Advanced Materials Research | Year: 2011

Three kinds of low cost shielding materials using boron-containing ores and epoxy as starting materials were developed. The three boron-containing ores consist of natural green ore that is specific in China and the two artificial minerals that are boron-containing iron ore concentrate and boron-rich slag. They were got after natural green ore dressing and separation from blast furnace, respectively. The shielding performance of slow neutron and 60Co γ ray among the three shielding materials were compared. The results show that boron-rich slag as neutron absorber performs relative good slow neutron shielding ability, its macroscopic cross section (σ) is 0.271cm-1 which is about 1.72 times higher than Lead-Boron Polyethylene B201 whose macroscopic cross section (σ) is 0.158cm -1. Boron-containing iron ore concentrate/epoxy composite performs relative good 60Co γ ray shielding ability and its linear attenuation coefficient (μ) is 0.0772cm-1. The elements boron and iron that exist as compound in ore are the main reasons to affect the slow neutron shielding performance. The iron element that exists as compound in the ore has the main attribution to 60Co γ ray shielding. © (2011) Trans Tech Publications.


Li Z.-F.,Northeastern University China | Li Z.-F.,Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials | Xue X.-X.,Northeastern University China | Xue X.-X.,Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials | And 2 more authors.
Gongneng Cailiao/Journal of Functional Materials | Year: 2010

A low cost shielding material using boron-containing iron ore concentrate and low viscosity epoxy E51 as starting materials was developed. Boron-containing iron ore concentrate was got after green ore containing boron dressing which is specific in China. Experiments were performed in order to determine the characteristics of the low cost composite, such as slow neutron and 60Co γ shielding performance. Confirmed the optimum mixture ratio of epoxy to boron-containing iron ore concentrate. Testified the feasibility of using boron-containing iron ore concentrate as starting material to prepare the shielding material. The results showed that slow neutron cross-section of three samples proportioning are all larger than lead-boron polyethylene shielding material B201, which cross-section is Σ=0.158 cm-1 and loaded with B4C as neutron absorber. The largest cross-section among the samples is Σ=0.1882 cm-1 and performs good slow neutron shielding ability. The 60Co γ shielding performance is between water and concrete, the largest linear attenuation coefficient of samples is μ=0.0772 cm-1.


Li Z.-F.,Northeastern University China | Li Z.-F.,Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials | Xue X.-X.,Northeastern University China | Xue X.-X.,Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials
Dongbei Daxue Xuebao/Journal of Northeastern University | Year: 2011

Boron-containing green ore in the eastern area of Liaoning Province of China, boron-containing iron ore concentrate and boron-rich slag were used as starting materials to prepare boron-containing composites. Monte-Carlo method was used to study the shielding properties of boron-containing ore/epoxy composites with different proportions for slow neutrons of 1 keV, 1 eV, 0.0253 eV energy respectively and the factors that affect the shielding abilities, and comparison with shielding materials of Portland cement concrete was also conducted. The results show that the shielding properties of the composites for 1keV neutron increase with the increase of hydrogen content in the composites. The shielding performance of the composites for 1eV neutron is mainly related to boron content and the ratio of boron to hydrogen in the mixture. Boron content is the main f actor that affects the shielding properties for 0.0253 eV neutron. The slow neutron shielding properties of all composites are stronger than Portland cement concrete and the boron-containing ore/epoxy composites are expected to improve the shielding properties of Portland cement concrete. This may provide the basis for the design of slow-neutron shielding.


Cao X.,Northeastern University China | Cao X.,Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials | Xue X.,Northeastern University China | Xue X.,Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials | And 5 more authors.
TMS Annual Meeting | Year: 2010

A new style TiB2/UHMWPE composite shielding material for nuclear radiation was prepared by hot pressing method. The microstructure, mechanical property and radiation shielding of composite material were analyzed. The results indicate that each component was distributed continuously, evenly and the interface was combined closely. Hardness and tensile strength of the composite improved with TiB2 content increased. The absorption ratio for thermal neutron increased with the thickness of composite increased.


Li Z.-F.,Northeastern University China | Li Z.-F.,Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials | Xue X.-X.,Northeastern University China | Xue X.-X.,Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2011

Using the special boron-containing ores in the eastern area of Liaoning Province of China, boron-containing wastes and epoxy as studying object, total mass attenuation coefficients (MAC) of photon for five kinds of materials including ludwigite ore, boron-containing iron ore concentrate, boron rich slag, common boron mud and epoxy at the photon energy from 1 keV to 100 GeV were calculated theoretically, which can provide the data for design of peripheral shielding of radioactive isotopes source, reactor and the particle accelerator. The results show that the addition of boron-containing ores to epoxy leads to obvious variation in total MAC. Photoelectric effect is dominant at the energy ranging from 1 keV to 0.1 MeV. The MAC of boron containing ores varies considerably in this energy range and the K edge of the elements in the ores increases the total MAC greatly. Compton scattering is the main interaction at photon energy from 0.1 MeV to 10 MeV and the total MAC is not sensitive to the photon energy in this range, and the MAC of epoxy is higher than ores in this range. The photon MAC insignificantly increases at photon energy ranging from 10 MeV to 100 GeV and the main interaction is pair production in this range. Boron containing iron ore concentrate is the best photon absorber in this energy range.


Li Z.-F.,Northeastern University China | Li Z.-F.,Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials | Xue X.-X.,Northeastern University China | Xue X.-X.,Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2011

Using the boron-containing iron ore concentrate and boron-rich slag as studying object, the starting materials were got after the specific green ore containing boron dressing in China and blast furnace separation respectively. Monte-Carlo method was used to study the effect of the boron-containing iron ore concentrate and boron-rich slag and their composites with epoxy on the neutron shielding abilities. The reasons that affecting the shielding materials properties was discussed and the suitable proportioning of boron-containing ore to epoxy composites was confirmed; the 14.1 MeV fast neutron removal cross section and the total thermal neutron attenuation coefficient were obtained and compared with that of the common used concrete. The results show that the shielding property of 14.1 MeV fast neutron is mainly concerned with the low-Z elements in the shielding materials, the thermal neutron shielding ability is mainly concerned with boron concentrate in the composite, the attenuation of the accompany γ-ray photon is mainly concerned with the high atom number elements content in the ore and the density of the shielding material. The optimum volume fractions of composites are in the range of 0.4-0.6 and the fast neutron shielding properties are similar to concrete while the thermal neutron shielding properties are higher than concrete. The composites are expected to be used as biological concrete shields crack injection and filling of the anomalous holes through the concrete shields around the radiation fields or directly to be prepared as shielding materials.

Loading Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials collaborators
Loading Liaoning Key Laboratory for Ecologically Comprehensive Utilization of Boron Resources and Materials collaborators