The requirements regarding the weight and capacity reduction of neutron shielding materials have become an urgent issue for advanced nuclear facilities and plants. An epoxy-based neutron shielding material with high-temperature stability and good neutron irradiation resistance was designed in this paper to solve the above issue. Aminophenol trifunctional epoxy resin (AFG-90H) was compounded with samarium oxide (SmO) by means of an ultrasonic-assisted method and the compatibility of SmO with the AFG-90H matrix was improved by 3-aminopropyltriethoxysilane (APTES) surface modification. Fabricated SmO-APTES/AFG-90H composites exhibited improved thermal stability, glass transition temperature and Young's modulus with increased SmO-APTES content. Neutronics calculation results show that the neutron permeability of 2 mm-thick 30 wt% SmO-APTES/AFG-90H was 98.9% higher than that of the AFG-90H matrix under the irradiation of the thermal neutron source. The results show that the proper addition range of SmO-APTES is between 20% and 25%. The SmO-APTES/AFG-90H composite is a promising neutron shielding material for advanced nuclear system.
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http://dx.doi.org/10.3390/polym14030638 | DOI Listing |
Luminescence
January 2025
Department of Physics, Manipal Institute of Technology, Manipal Academy of Higher Education, Manipal, India.
Eu-Gd co-doped glasses composed of 15BO-12SiO-(40-x)TeO-3EuO-xGdO-12BiO-8BaO-10ZnO with x = 0-4 mol% (coded as EuGd-x) were fabricated using melt quench approach to develop transparent radiation shielding system. Their structural, optical and mechanical properties were examined. 5.
View Article and Find Full Text PDFAppl Radiat Isot
March 2025
Experimental Nuclear Physics Department, Nuclear Research Centre, Egyptian Atomic Energy Authority, Egypt; Cyclotron Facility, Egyptian Atomic Energy Authority, Egypt.
Neutron and gamma-ray shielding design for a 30Ci (1.11TBq) Am-Be irradiation facility is studied using MCNP5 Monte Carlo simulation code. The study focuses on the optimization of the shielding layers of the previously planned neutron irradiation facility.
View Article and Find Full Text PDFHealth Phys
January 2025
China Medical University Hospital, No. 2, Yude Road, Taichung, Taiwan.
The shielding performance and activation susceptibility of a sandwich wall in the proton therapy facility of China Medical University Hospital were investigated in an integrated manner using FLUKA Monte Carlo simulations. The 2-m-thick partition wall between two adjoining treatment rooms had a three-layered structure, which comprised a 0.2-m-thick iron layer sandwiched between two layers of 0.
View Article and Find Full Text PDFSci Rep
January 2025
Physics Department, Faculty of Science, Fayoum University, Fayoum, Egypt.
For the purpose of this study, four natural rock samples-namely, diorite, granodiorite, tonalite, and granite-are being investigated about their radiation attenuation. The elemental composition of the rocks was obtained through Energy dispersive X-ray spectroscopy (EDX) which examines the microstructural and localized area elemental analyses of the four rock samples. A Monte Carlo simulation (MCNP) was used to determine and evaluate the investigated samples.
View Article and Find Full Text PDFSci Rep
January 2025
Los Alamos National Laboratory, Los Alamos, NM, 87544, USA.
Detecting shielded special nuclear material, such as nuclear explosives, is a difficult challenge pursued by non-proliferation, anti-terrorism, and nuclear security programs worldwide. Interrogation with intense fast-neutron pulses is a promising method to characterize concealed nuclear material rapidly but is limited by suitable source availability and proven instrumentation. In this study we have pioneered a demonstration of such an interrogation method using a high-intensity, short-pulse, laser-driven neutron source that offers potential benefits compared to conventional neutron sources.
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