Data Correction Method for Improving the Spatial Resolution of a Position-Sensitive 10B Neutron Detector

Karaevsky, S. Kh.; Potashev, S. I.; Drachev, A. I.; Burmistrov, Yu. M.

doi:10.1134/s1063778819120147

Cited by 3 publications

(1 citation statement)

References 6 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…High-energy neutrons (>1 MeV) first undergo inelastic scattering with substances with high atomic numbers and then lose energy, or undergo multiple elastic scattering with materials rich in hydrogen and then reduce energy to thermal neutrons (~eV). Thermal neutrons are easily captured or absorbed by elements with high neutron absorption cross-sections [ 8 ]. As described above, traditional shielding materials are roughly divided into metal, concrete and polymer materials according to their compositions.…”

Section: Introductionmentioning

confidence: 99%

Influences of Modified Sm2O3 on Thermal Stability, Mechanical and Neutron Shielding Properties of Aminophenol Trifunctional Epoxy Resin

2022

View full text Add to dashboard Cite

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 (Sm2O3) by means of an ultrasonic-assisted method and the compatibility of Sm2O3 with the AFG-90H matrix was improved by 3-aminopropyltriethoxysilane (APTES) surface modification. Fabricated Sm2O3-APTES/AFG-90H composites exhibited improved thermal stability, glass transition temperature and Young’s modulus with increased Sm2O3-APTES content. Neutronics calculation results show that the neutron permeability of 2 mm-thick 30 wt% Sm2O3-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 Sm2O3-APTES is between 20% and 25%. The Sm2O3-APTES/AFG-90H composite is a promising neutron shielding material for advanced nuclear system.

show abstract

Section: Introductionmentioning

confidence: 99%