scholarly journals Research on Thermal Neutron Shielding Performance of TiB2-Al Composite Materials

2021 ◽  
Author(s):  
Chao Wang ◽  
Zhefu Li ◽  
Mengge Dong ◽  
Lu Zhang ◽  
Jianxing Liu ◽  
...  
Keyword(s):  
Thermal Neutron ◽  
Cross Section ◽  
Neutron Fluence ◽  
Thermal Neutrons ◽  
Neutron Shielding ◽  
Preparation Methods ◽  
Neutron Fluence Rate ◽  
Maximum Value ◽  
Al Composite ◽  
Macroscopic Cross Section

<p>Although the various excellent properties and preparation methods of TiB<sub>2</sub>-based composites have been extensively studied, their neutron shielding properties have not received as much attention. In this article, the neutron shielding performance of the previously prepared TiB<sub>2</sub>-Al composite will be studied. The photo neutron source device was used to carry out neutron irradiation tests on test samples with a thickness of 10 mm. The average thermal neutron shielding rate of TiB<sub>2</sub>-based boron-containing composites is 17.55%, and the shielding rate increases with the increase of BN content. The macroscopic cross-section of thermal neutrons of the composites generally shows a stable trend, and when the BN content is 10%, the thermal neutrons macroscopic cross section reaches the maximum value of 7.58cm<sup>-1</sup>. With the increase of the BN content, the thermal neutron fluence rate shows a gradually decreasing trend.</p>

scholarly journals Research on Thermal Neutron Shielding Performance of TiB2-Al Composite Materials

2021 ◽  
Author(s):  
Chao Wang ◽  
Zhefu Li ◽  
Mengge Dong ◽  
Lu Zhang ◽  
Jianxing Liu ◽  
...  
Keyword(s):  
Thermal Neutron ◽  
Cross Section ◽  
Neutron Fluence ◽  
Thermal Neutrons ◽  
Neutron Shielding ◽  
Preparation Methods ◽  
Neutron Fluence Rate ◽  
Maximum Value ◽  
Al Composite ◽  
Macroscopic Cross Section

<p>Although the various excellent properties and preparation methods of TiB<sub>2</sub>-based composites have been extensively studied, their neutron shielding properties have not received as much attention. In this article, the neutron shielding performance of the previously prepared TiB<sub>2</sub>-Al composite will be studied. The photo neutron source device was used to carry out neutron irradiation tests on test samples with a thickness of 10 mm. The average thermal neutron shielding rate of TiB<sub>2</sub>-based boron-containing composites is 17.55%, and the shielding rate increases with the increase of BN content. The macroscopic cross-section of thermal neutrons of the composites generally shows a stable trend, and when the BN content is 10%, the thermal neutrons macroscopic cross section reaches the maximum value of 7.58cm<sup>-1</sup>. With the increase of the BN content, the thermal neutron fluence rate shows a gradually decreasing trend.</p>

Effect of Boron Carbide Content on Properties of Thermoplastic Natural Rubber Composite as Thermal Neutron Shielding

2017 ◽  
Vol 888 ◽  
pp. 179-183
Author(s):  
Nurazila Mat Zali ◽  
Hafizal Yazid ◽  
Megat Harun Al Rashid Megat Ahmad ◽  
Irman Abdul Rahman ◽  
Yusof Abdullah
Keyword(s):  
Tensile Strength ◽  
Natural Rubber ◽  
Boron Carbide ◽  
Thermal Neutron ◽  
Cross Section ◽  
Weight Percent ◽  
Neutron Shielding ◽  
Blending Method ◽  
Macroscopic Cross Section ◽  
Thermoplastic Natural Rubber

In this work, thermoplastic natural rubber (TPNR) composites were produced through melt blending method. Boron carbide (B4C) as filler was added into the polymer blend (TPNR) with different weight percent from 0% to 30% and the effect of different B4C contents on mechanical and thermal neutron attenuation properties of TPNR composites has been studied. The phase formation in composites was analyzed using XRD technique. From the results, it showed that the incorporation of B4C fillers into TPNR matrix has enhanced the macroscopic cross section of the composites, however it lessens the tensile strength. Macroscopic cross section of the composites were increased from 3.34 cm-1 to 14.8 cm-1, while the tensile strength of the composites decreased from 3.79 MPa to 1.06 MPa with increasing B4C from 0 wt% to 30 wt%. B4C diffraction peaks were also increased in intensity with increasing B4C content.

ABSOLUTE MEASUREMENT OF 14.57 MeV NEUTRON FLUENCE RATE USING PROTON RECOIL NEUTRON TELESCOPE

2020 ◽  
Vol 190 (3) ◽  
pp. 307-319
Author(s):  
Shobha Ghodke ◽  
V Sathian ◽  
Yashoda Singh ◽  
Tarun Patel ◽  
S Santra
Keyword(s):  
Cross Section ◽  
Copper Foil ◽  
Neutron Fluence ◽  
Scattering Cross Section ◽  
Fluence Rate ◽  
Total Uncertainty ◽  
Neutron Fluence Rate ◽  
Scattering Cross ◽  
Foil Activation ◽  
Proton Recoil

Abstract A single stage vacuum-type proton recoil neutron telescope (PRT) was used for accurate measurement of 14.57 MeV neutron fluence rate from an indigenously developed D-T neutron generator at Purnima, BARC. The telescope consists of a polyethylene radiator having 4 cm diameter and CsI (Tl) scintillation crystal having thickness 1.5 mm and 4 cm diameter separated by 20.5 cm kept in a vacuum chamber. The neutron detection efficiency of the telescope for 14.57 MeV neutrons was calculated analytically using n-p scattering cross section data from Evaluated Nuclear Data File VII and also evaluated using fluka simulation. The relativistic transformation of n-p differential scattering cross section from centre-of-mass to laboratory system was used for calculating the efficiency of PRT. The 14.57 MeV neutron fluence rate was also measured using copper foils. The comparison of fluence rate measured using PRT and copper foil activation techniques is presented in this paper. The total uncertainty in measurement using PRT and copper foil activation technique is found to be 3.93 and 6.97%, respectively.

Study on the Properties of Boron-Containing Ores/Epoxy Composites for Slow Neutron Shielding

2011 ◽  
Vol 201-203 ◽  
pp. 2767-2771 ◽  
Author(s):  
Zhe Fu Li ◽  
Xiang Xin Xue ◽  
Tao Jiang ◽  
He Yang ◽  
Mi Zhou
Keyword(s):  
Cross Section ◽  
Iron Ore ◽  
Low Cost ◽  
Slow Neutron ◽  
Linear Attenuation Coefficient ◽  
Neutron Shielding ◽  
Neutron Absorber ◽  
Macroscopic Cross Section ◽  
Γ Ray ◽  
Iron Ore Concentrate

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.

Benzoxazine resin as an interesting building block for advanced neutrons shields

2021 ◽  
pp. 095400832110218
Author(s):  
Oussama Mehelli ◽  
Mehdi Derradji ◽  
Abdelmalek Habes ◽  
Nour Elislem Leblalta ◽  
Raouf Belgacemi ◽  
...  
Keyword(s):  
Cross Section ◽  
Research Reactor ◽  
Building Blocks ◽  
Mean Free Path ◽  
Sample Thickness ◽  
Experimental Setup ◽  
Reinforced Composites ◽  
Neutron Shielding ◽  
Recent Developments ◽  
Macroscopic Cross Section

The design of lightweight neutrons shields has been restricted for quite some time to the use of the epoxy thermosets as the main building blocks. Meanwhile, the recent developments in the field of polymers suggest otherwise. Indeed, benzoxazine resins have taken the lead over the traditional thermosets in many exigent applications. Therefore, in a vision to introduce newer matrices with better performances and to further expand the applications of the benzoxazine resins into the nuclear field, the neutron shielding efficiency along with the thermal and thermomechanical performances of the neat benzoxazine polymer and its subsequent B4C-reinforced composites were investigated. The neutron shielding measurements were performed using an optimized experimental setup at NUR research reactor, Algiers. The neat benzoxazine polymer displayed almost similar thermal neutrons screening performances than the epoxy with a macroscopic cross-section (Σ) of a 0.724 cm− 1 equivalent to a mean free path (λ) of 0.957 cm. The effect of the particle amount was also studied to maximize the shielding ability of the developed materials. For instance, the benzoxazine composite containing 20 wt.% of B4C displayed the outstanding screening ratio of about 96% for a sample thickness of 13 mm. Finally, the remarkable findings were put into context by providing multifaceted comparisons with the available shielding materials.

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