• Korean Chemical Engineering Research
• /
• 제57권3호
• /
• pp.368-371
• /
• 2019

Using first principles calculations we investigated the thermomechanical stability of spent nuclear fuels (SNF), especially how mechanical properties of $UO_2$, such as, bulk, shear and Young's moduli and Poisson's ratio vary through alpha-decay of U into Th with generation of He gas. Our results indicate that substitution of U by Th through alpha decay ($U_{1-x}Th_xO_2$) does not significantly affect the stability of the grain in a fuel matrix. In addition, we studied the transport properties of He in and boundaries of the $U_{1-x}Th_xO_2$ grain. Helium preferentially resides at the grain boundaries through diffusion. Our study can contribute to substantial reduction of environmentally risk and enhancement of our sustainability by safe control of radioactive materials.

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2004년도 학술논문집
• /
• pp.105-114
• /
• 2004

This study investigated the thermal behavior of the nuclear graphite waste generated from the decommissioning of the Korean nuclear research reactor, The first part study investigated the decomposition rate of the nuclear graphite waste up to $1000^{\circ}C$ under various oxygen partial pressures using a thermo-gravimetric analyzer (TGA). Tested graphite waste sample not easily destroyed in the oxygen-deficient condition. However, the gas-solid oxidation reaction was found to be very effective in the presence of oxygen. No significant amount of the product of incomplete combustion was formed even in the limited oxygen concentration of 4% $O_2$. The influence of temperature and oxygen partial pressure was evaluated by the theoretical model analysis of the thermo-gravimetric data. The activation energy and the reaction order of graphite oxidation were evaluated as 128 kJ/mole and 1.1, respectively. The second part of this study investigated the behavior of radioactive elements under graphite oxidation atmosphere using thermodynamic equilibrium model. $^{22}Na$, $^{134}Cs$ and $^{137}Cs$ were found be the semi-volatile elements. Since volatile uranium species can be formulated at high temperatures above $1050^{\circ}C$, the temperature of incinerator furnace should be minimized. Other corrosion/activation products, fission products and uranium were found to be the non-volatile species.

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2005년도 추계 학술대회 논문집
• /
• pp.69-78
• /
• 2005

유리화공정 고온영역에서의 방사성 배기체 유동해석을 통하여 해석에 적합한 모델을 개발하였다. 개발된 모델을 이용한 수치해석을 통하며 유리화공정 원형설비에 영향을 미치는 인자를 파악하였는데, 저온용융로. 배관냉각기 및 고온필터 등의 세 단계로 나누어 해석을 수행하였다. 저온용융로의 경우 폐기물 처리용량에 따른 해석과 저온용융로 내부 과잉산소 공급 비에 따른 연소지연 가능성에 대한 수치해석을 수행하였다. 배관냉각기의 경우에는 각종 수치 모델 및 외벽 열전달계수를 확보하였으며 또한 방사성 핵종의 거동을 모사할 수 있는 수치적 모델을 개발하였다. 이러한 방법론을 적용하여 핵종의 열교환기 내부에서의 응고 특성에 대하여 고찰하였다. 수평 유입형식의 인입관이 있는 일반적인 형상과 유입구가 필터 내부에 수직으로 있는 고온필터의 수치해석을 통하여 인입관의 위치에 따른 고온필터의 작동 특성을 비교하였다.

• 방사성폐기물학회지
• /
• 제18권2호
• /
• pp.169-177
• /
• 2020

Here, the stability of stainless steel 316 (SS-316) was investigated to identify its applicability in the oxide reduction process, as a component in related equipment, to produce a complicated gas mixture composed of O₂ and Cl₂ under an argon (Ar) atmosphere. The effects of the mixed gas composition were investigated at flow rates of 30 mL/min O₂, 20 mL/min O₂ + 10 mL/min Cl₂, 10 mL/min O₂ + 20 mL/min Cl₂, and 30 mL/min Cl₂, each at 600℃, during a constant argon flow rate of 170 mL/min. It was found that the corrosion of SS-316 by the chlorine gas was suppressed by the presence of oxygen, while the reaction proceeded linearly with the reaction time regardless of gas composition. Surface observation results revealed an uneven surface with circular pits in the samples that were fed mixed gases. Thermodynamic calculations proposed the combination of Fe and Ni chlorination reactions as an explanation for this pit formation phenomenon. An exponential increase in the corrosion rate was observed with an increase in the reaction temperature in a range of 300 ~ 600℃ under a flow of 30 mL/min Cl₂ + 170 mL/min Ar.

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
• /
• pp.60-63
• /
• 2004

Sulfurization of rare-earth oxides R203 (R=Nd, Eu) using sulfurizing reagents, such as $H_2S$ and $SC_2$was examined for the sulfide magnetic separation of spent fuel. $EU_2O_3$was found to react with H$_3$S gas forming the mixture of $EU_2O_2S$ and EuS at 500 oC, while EuS was formed by $SC_2$ at 800 oC. In the case of the mixture of $R_2O_3$and $UO_2$, EuS and $ND_3S_4$ were formed as well as $EU_2O_2S$ and $Nd_2O_2S$ at 500oC in $H_2S$, though $UO_2$ remained unreacted.

• Nuclear Engineering and Technology
• /
• 제2권3호
• /
• pp.179-183
• /
• 1970

Solanum andigena의 광주성 주기중의 방사성 콜레스테롤의 대사를 연구하였다. 대사산물로서 방사성 솔라닌과 그 가수분해물 솔라니딘을 분리 결정화하였으며, 콜레스테롤은 이 식물체 내에서 형성되는 에스테르화된 형태로 분리하였다. 단일 및 장일식물간의 콜레스테롤을 대사에는 뚜렷한 차이는 찾아 볼 수 없으나. 괴경중의 스테로이드 알카로이드에 콜레스테롤이 관여하고 있는 것으로 논의되었다.

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
• /
• pp.238-244
• /
• 2004

The relationship between the leaching and gap inventory of spent fuel has been studied. When a specimen of J44H08 spent PWR fuel with 38 GWD/MTU has been leached in the synthetic granitic groundwater in Ar atmosphere, the released fraction of cesium was increased rapidly up to 0.7% at around 500 days and stayed below 0.8% until 3 years. This 0.7% of cesium might be released from the gap in this fuel. The measurement of gap inventory with C15I08 spent PWR fuel, having 35 GWD/MTU and 0.22% of fission gas release, was also determined near 0.6% for the cesium, which is a similar fraction of cesium released from the leaching experiment with J44H08 fuel. Its gap inventories of strontium and iodine were about 0.03 and less than 0.2% respectively. Respective fractions of cesium and strontium in grain boundary of C15I08 were 0.78, 0.09%.

• 방사성폐기물학회지
• /
• 제16권3호
• /
• pp.301-308
• /
• 2018

핵분열로 인해 생성되는 방사성 노블가스는 주변국의 핵활동을 감시할 수 있는 중요한 지표 핵종이다. 특히 제논은 생성량이 많고 반감기가 짧아 핵실험 탐지에 적합하며 크립톤은 핵연료 재처리 탐지의 추적자로 활용되고 있다. 방출된 방사성 노블가스는 막대한 대기에 희석되어 농도가 감소하고 일부는 시간에 따라 방사능이 감쇠하기 때문에 대기 중에는 매우 극미량으로 존재하게 된다. 따라서 측정을 통해 의미 있는 데이터를 얻기 위해서는 가능한 낮은 수준의 MDA를 설정하는 것이 중요하다. 본 연구에서는 방사성 제논과 크립톤을 동시 포집 할 수 있는 장비인 BfS-IAR시스템을 활용하여 이론을 통해 MDA를 산출하였다. 또한 MDA 산출방식의 변화, 신뢰수준의 정도는 물론 계측 조건의 변화에 따른 영향을 확인하고 MDA를 저감하기 위한 방안들을 모색하였다. 그 결과 배경농도가 극미량인 제논의 경우 전처리과정의 효율화와 안정적인 계측 성능유지가 가장 중요한 요소로 판단되었으며, 크립톤의 경우 제논과 달리 시료의 방사능이 높기 때문에 MDA 재설정을 통한 분석조건이나 시스템 최적화를 통해 효율적인 분석을 수행할 수 있을 것으로 판단된다.

• Nuclear Engineering and Technology
• /
• 제56권5호
• /
• pp.1781-1795
• /
• 2024

This study investigated the levels of radioactivity in soil surrounding a phosphate fertilizer factory in Egypt, aiming to assess potential risks to the population exposed to radiation. Concentrations of ²³⁸U, ²²⁶Ra, ²³²Th, and ⁴⁰K were measured in soil samples collected from two subsites: one near the factory (subsite 1) and another further away (subsite 2). Two different systems were used for measuring radioactivity, a high-purity gamma ray spectroscopy system with an HPGe detector for gamma-emitting isotopes and a CR-39 solid nuclear track detector for alpha-emitting radon gas. Subsite 1, located close to the factory, displayed significantly elevated levels of ²²⁶Ra compared to global background levels (514 and 456 Bq/kg vs. 35 Bq/kg). Additionally, the concentrations of ²³⁸U (241.06 Bq/kg vs. global average 35 Bq/kg), ²³²Th (16.15 Bq/kg vs. global average 30 Bq/kg), and ⁴⁰K (146.36 Bq/kg vs. global average 400 Bq/kg) were all above global averages. Furthermore, a high concentration of radon gas (337.06 μSv/y) was measured at subsite 1. The strong positive correlation observed between ²²⁶Ra and ²³⁸U (0.96256) provides further evidence of potentially elevated radioactivity levels near the factory. In contrast, subsite 2, situated farther from the factory, exhibited natural radioactive background levels within international limits. Quantitative analysis revealed that gamma ray absorbed doses for ²²⁶Ra and ²³²Th exceeded global averages in some samples. Specifically, ²²⁶Ra doses ranged from 7.8 to 46.26 ppm (exceeding the 20 ppm global average in some cases), and ²³²Th doses ranged from 1.98 to 9.14 ppm (exceeding the 10 ppm global average in some cases). The concentration of ⁴⁰K, however, remained within the global range (0.07%-0.69 %). The observed imbalances in the ratios of Th/U (0.17-0.24 Bq/kg and 0.73-0.24 ppm) and U/Ra (0.81-0.73 Bq/kg and 0.73-0.17 ppm), both of which are significantly lower than their respective global averages of 4 and 2.4, point towards the presence of fertilizer-derived contamination. This conclusion is further supported by the high phosphate concentrations detected in the samples. Overall, this study suggests that radioactive contamination near the phosphate fertilizer factory significantly exceeds global background levels and international limits in some cases. This raises concerns about potential risks posed to surrounding agricultural land and crops.

• 청정기술
• /
• 제14권2호
• /
• pp.110-116
• /
• 2008

원자력산업이 발생하는 방사성폐기물은 고체, 액체 그리고 기체상으로 구분된다. 특히 기체상 방사성폐기물인 방사성 메틸요오드는 활성탄을 이용하여 흡착된다. 이때 활성탄에는 방사성 메틸요오드를 보다 효율적으로 포집하기 위해 5 wt%의 트리에틸렌다이아민 (Trietylenediamine; 1,4-diazania-bicycle[2.2.2]octane, TEDA)이 첨착되어 있다. 일반적으로 대기중에서 TEDA와 메틸요오드($CH_3I$)는 I-TEDA(TEDA와 메틸요오드 결합물)를 형성하게 된다. 방사성 요오드를 포집한 방사성 폐 활성탄을 재사용하기 위해서는, 이러한 형태의 I-TEDA를 제거해야 하는데, 현재는 아세토나이트릴을 이용한 습식재활용법이 개발되었다. 그러나 이러한 습식재활용법은 다량의 2차폐기물을 발생하는 문제점이 있기 때문에, 본 연구에서는 I-TEDA를 제거하기 위한 방법으로 초임계이산화탄소를 기본용매로써 사용하였으며, 수정미량저울(Quartz Crystal Microbalance, QCM)을 이용하여 I-TEDA의 제거율을 측정하였다. 실험결과 I-TEDA를 제거하기 위해 추출을 위한 첨가용액으로 메탄올이 가장 적합하였고, 최적화된 온도, 압력 및 추출용매의 유량조건을 찾아내었다. 이러한 결과를 바탕으로 하여 방사성 폐활성탄으로부터 I-TEDA를 제거할 수 있는 가능성에 대한 검토를 하였다.