A radiation shielding resin with thermal stability and high radiation shielding effect has been developed for the neutron shielding resin filled in the shielding shell of dry storage/transport cask for spent nuclear fuel. Among the most commercially available neutron shielding resins, epoxy and aluminum hydroxide boron carbide are used. But in case of the resin, hydrogen content enhances the neutron shielding effect through optimization of aluminum hydroxide, zinc borate, boron carbide, and flame retardant. We developed a radiation shielding material that can increase the boron content and have thermal stability. Flame retardancy was evaluated for thermal stability, and neutron shielding evaluation was conducted in a research reactor to prove the shielding effect. As a result of the UL94 vertical burning test, a grade of V-0 was received. Therefore, it was confirmed that it had flame retardancy. According to an experiment to measure the shielding rate of the resin against neutron rays using NRF (Neutron Radiography Facility), a shielding rate of 91.54% was confirmed for the existing resin composition and a shielding rate of 96.30% for the developed resin composition. A 40 M SANS (40 M Small Angle Neutron Scattering Instrument) neutron shielding rate test was performed. Assuming aging conditions (6 hours, 180 degrees), the shielding rate was analyzed after heating. As a result of the experiment, the developed products with 99.8740% and 99.9644% showed the same or higher performance.

A purpose of the present study is to derive optimum study factors for removal of heavy metals using combinedalternating current electric/magnetic field and electric membranes for the area contaminated with heavy metals in soil orunderground water. ORP (Oxidation Reduction Potential) analysis was conducted to determine an intensity of tendencyfor oxidation or reduction of the samples contaminated with heavy metals, and electrical membrane treatment was usedwith adjustment of concentrations and voltages of liquid electrode to derive a high removal rate. Then, electrolysis wascarried out to collect deposits, and electrical conductivity increased again. However, as time passed, the ions weredecomposed, and ionic bonds of the heavy metals started to decompose due to a magnetized water device connected toeach line, resulting in gradual stabilization. Gas generated at the electrode is reduced with production of low heat resultingin an increased reaction rate, accompanied by no oxidation in anion exchange membrane and cation exchange membranewithout occurrence of a reduction phenomenon. Also power consumption may be reduced with a small amount ofelectricity, and treatment efficiency was also shown to be increased.