Although monitoring of radon has been extensively implemented throughout South Korea, the risk assessment has been mainly limited to indoor environments such as schools, workplaces, and multi-use facilities, and evaluations have normally been performed separately. In this study, the differences in radon exposure according to two groups (< 1 and 1-6 years old) were evaluated considering various indoor and outdoor environments, timeactivity patterns, variations in radon concentrations, and dwelling type (single detached and apartment house) using Monte-Carlo simulation. The distribution and representative values of radon concentration by micro-environments were confirmed through the Anders-Darling test, and a uniform distribution was applied in case of uncertainty. The effective dose ranged from 1.81 ± 1.19 to 2.81 ± 3.02mSv/y. Comparing the levels recommended by EPA, WHO, and ICRP with the value of the 95th percentile of this study, it was found that the results for those dwelling in detached houses exceeded recommended levels. Infants that spend a lot of time in homes with relatively high levels of concentration of radon are assessed to be somewhat more vulnerable to radon exposure.

In aluminum electrolysis, sodium penetration into carbon cathodes is considered as the main cause of cell failure and efficiency loss, but the detailed mechanism is still not definitely clear. Since the macroscopic properties of material depend on the microscopic structures, a large-scale atomistic model of anthracite cathodes was constructed to represent several important structural characteristics. Combined with Monte Carlo and molecular dynamics simulations, the adsorption and diffusion behaviors of sodium were investigated, respectively. The results suggest that sodium adsorption mainly occurs in the larger micro-pores with the range of 10–19 Å, while it accords well with to type-I Langmuir adsorption model. The sodium is found to be preferentially adsorbed in arch-like structures with 5- or 7-membered rings or around heteroatom, especially oxygen. Moreover, the movements of sodium through carbon matrix mainly depend on the continuous diffusive motion while most sodium particles tend to be trapped in voids with small mobility. The calculated transport diffusion coefficient is equal to 6.132 × 10− 10 m2/ s, which is in outstanding agreement with experimental results. This fundamental research would contribute to the understanding of sodium penetration mechanism and the optimization of cathode industry in the future.

Plastic scintillators can be used to find radioactive sources for portal monitoring due to their advantages such as faster decay time, non-hygroscopicity, relatively low manufacturing cost, robustness, and easy processing. However, plastic scintillators have too low density and effective atomic number, and they are not appropriate to be used to identify radionuclides directly. In this study, we devise the radiation sensor using a plastic scintillator with holes filled with bismuth nanoparticles to make up for the limitations of plastic materials. We use MCNP (Monte Carlo N-particle) simulating program to confirm the performance of bismuth nanoparticles in the plastic scintillators. The photoelectric peak is found in the bismuth-loaded plastic scintillator by subtracting the energy spectrum from that of the standard plastic scintillator. The height and diameter of the simulated plastic scintillator are 3 and 5 cm, respectively, and it has 19 holes whose depth and diameter are 2.5 and 0.2 cm, respectively. As a gamma-ray source, Cs-137 which emits 662 keV energy is used. The clear energy peak is observed in the subtracted spectrum, the full width at half maximum (FWHM) and the energy resolution are calculated to evaluate the performance of the proposed radiation sensor. The FWHM of the peak and the energy resolution are 61.18 keV and 9.242% at 662 keV, respectively.

The present multidisciplinary study, which is a nexus of engineering and political science, investigates how the modernization of Non-Strategic Nuclear Weapons (NSNWs) affects the IAEA safeguards system based on the likelihood of the use of nuclear weapons. To this end, this study examines the characteristics of modernized NSNWs using Monte Carlo techniques. The results thus obtained show that 10 kt NSNWs with a Circular Error Probability (CEP) of 10 m can destroy the target as effectively as a 500 kt weapon with a CEP of 100 m. The IAEA safeguards system shows that the Significant Quantity (SQ) of 1 of plutonium is 8 kg, a parameter that was established when strategic nuclear weapons were dominant. However, the results of this study indicate that in recent years, low-yield nuclear weapons such as NSNWs have been more strategically interesting than strategic nuclear weapons as NSNWs require less plutonium than strategic nuclear weapons. Therefore, we would like to conclude that reducing the SQ of plutonium can result in more robust safeguards and non-proliferation strategies.

연구에서는 기존의 납을 대체할 수 있는 의료 방사선 차폐제품 적용을 위해 몬테카를로 시뮬레이션을 통해 바륨화합물의 두께별 차폐능을 모의 추정하였다. 차폐재 물질로는 황산바륨(BaSO4)을 이용하였고, 시편의 면적은 15 × 15 ㎠, 황산바륨의 밀도는 4.5 g/㎤ , 납의 밀도 11.34 g/㎤를 적용하여 차폐재 시편의 두께를 0.1 ㎜부터 5 ㎜까지 시뮬레이션 하였다. 입력 선원은 연속 X-ray 에너지 스펙트럼(40 kVp ∼ 120 kVp)에서 10kVp Step으로 시뮬레이션하였다. 40 kVp ∼ 60 kVp에서의 흡수확률은 3 ㎜ ∼ 5 ㎜ 두께에서는 납과 동일한 차폐능을 나타내었으나, 2 ㎜ 이하에서는 차폐능이 기존 납 차폐재에 비해 다소 차폐능이 떨어지는 결과로 나타났다. 또한 70 kVp ∼ 120 kVp 에너지대역에서의 차폐능은 기존 납 차폐재와 유사한 성능을 보였지만, 0.5 ㎜ 이하에서는 다소 낮은 차폐능으로 모의 추정되었다. 본 연구는 몬테카를로 시뮬레이션을 통해 의료용 엑스선 에너지 대역에 대한 두께 함수로써 바륨화합물의 차폐능을 추정하여 기존의 납과 비교 분석하였다. 또한 순수한 황산바륨의 의료용 방사선 차폐제품 적용가능성을 검증하고자 하였다. 그 결과 의료 방사선 에너지 대역 70 kVp ∼ 120 kVp 에서 최소 2 ㎜ 이상의 바륨화합물 두께에서 기존납 1.5mm 대비 95% 이상의 차폐효과가 있는 것으로 추정되었으며, 본 결과는 의료용 방사선 차폐제품의 경량화 제작에 기초 자료로 제공될 수 있을 것으로 사료된다.