Abstract

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.

Highlights

  • Neutron radiation exists in nuclear reactors, and in various industrial, aviation and radiotherapy fields [1–4]

  • Divya et al pointed out that the serious problem with boron-containing stainless steels is the formation of low-melting point eutectics, makes this class of steel susceptible to heat cracking [9]

  • The results show that the thermoset polyimide matrixes exhibited high thermal stability with T5 > 800 ◦C both in nitrogen and air environments [23]

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Summary

Introduction

Neutron radiation exists in nuclear reactors, and in various industrial, aviation and radiotherapy fields [1–4]. The R&D on radiation protection materials is widely performed in the nuclear-related fields, including neutron shielding materials. Thermal neutrons are captured or absorbed by elements with high neutron absorption cross-sections [8]. Blending hydrogen-rich polymer matrix with high neutron cross-section absorbing elements can integrate neutron moderation and absorption. These materials are expected to become alternative materials for metals and concrete in nuclear facilities, such as polyethylene (PE) [14,15], high-density polyethylene (HDPE) [16,17], epoxy resin (EP) [18,19], ethylene propylene diene monomer (EPDM) [20] and polyimide (PI) [21,22], etc. Jiang et al blended B4C particles with AFG-90H to develop a new type of AFG-90H epoxy resin-based composite, and the results show good neutron shielding and mechanical performance at high temperatures [24]. It is usually used as an element in the Ag-In-Cd control rods of reactors [30]

Figure 2 in Section 2 “Experimental”
Surface Modification of Sm2O3 Powder
Fabrication of Sm2O3-APTES/AFG-90H
Results and Discussion
XRD Patterns of Sm2O3 and Sm2O3-APTES/AFG-90H Composite7sof 17
Morphology Analysis
Mechanical Properties of Sm2O3-APTES/AFG-90H
Conclusions
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