• Nuclear Engineering and Technology
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• 제56권2호
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• pp.707-714
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• 2024

Different degrees of natural radioactivity found in quartz can have negative consequences on health. Quartz vein along the investigated Abu Ramad area, Egypt, had its natural radioactivity assessed. The HPGe spectrometer was used to determine the role played by the radionuclides ²³⁸U, ²³²Th, and ⁴⁰K in the gamma radiation that was emitted, and the results showed that these concentrations are 484.64 ± 288.4, 36.8 ± 13.1 and 772.2 ± 134.6 Bq kg^-1 were higher than the corresponding reported global limits of 33, 45, and 412 Bq kg^-1 for each radionuclide (²³⁸U, ²³²Th, and ⁴⁰K). Among the radiological hazard parameters, the excess lifetime cancer risk (ELCR) is estimated and it's mean value of ELCR (1.2) is higher than the permissible limit of 0.00029. The relationship between the radionuclides and the associated radiological hazard characteristics was investigated based on multivariate statistical methods including Pearson correlation, principal component analysis (PCA), and hierarchical cluster analysis (HCA). According to statistical research, the radioactive risk of quartz is primarily caused by the ²³⁸U, ²³²Thand ⁴⁰K. Finally, applying quartz to building materials would pose a significant risk to the public.

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

• Nuclear Engineering and Technology
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• 제46권3호
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• pp.407-412
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• 2014

In this research, we investigated the burnup characteristics and the conversion of fertile $^{232}Th$ into fissile $^{233}U$ in the core of a Sodium-Cooled Fast Reactor (SFR). The SFR fuel assemblies were designed for burning $^{232}Th$ fuel (fuel pin 1) and $^{233}U$ fuel (fuel pin 2) and include mixed minor actinide compositions. Monte Carlo simulations were performed using Serpent Code1.1.19 to compare with CRAM (Chebyshev Rational Approximation Method) and TTA (Transmutation Trajectory Analysis) method in the burnup calculation mode. The total heating power generated in the system was assumed to be 2000 MWth. During the reactor operation period of 600 days, the effective multiplication factor (keff) was between 0.964 and 0.954 and peaking factor is 1.88867.

• Journal of Radiation Protection and Research
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• 제30권4호
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• pp.167-174
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• 2005

The concentrations of natural and artificial radionuclides in soil and gamma ray dose rate in air at 233 locations in Korea have been determined. The national mean concentrations of $^{232}Th,\;^{226}Ra,\;^{40}K,\;^{137}Cs\;and\;^{90}Sr$ in soil were $60{\pm}31,\;33{\pm}14,\;673{\pm}238,\;35{\pm}9.3\;and\;5.0{\pm}3.4\;Bq\;kg^{-1}$, respectively. The mean gamma-ray dose rate at 1 m above the ground was $7918\;nGy\;h^{-1}$. $^{137}Cs$ concentration had highly significant correlation with organic matter content and cation exchange capacity. $^{90}Sr$ concentration had slightly coherent with pH. The results have been compared with other global radioactivity and radiation measurements.

• 암석학회지
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• 제23권3호
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• pp.239-247
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• 2014

(U-Th)/He 연령측정법은 자연상에 존재하는 $^{238}U$, $^{235}U$ 및 $^{232}Th$이 붕괴할 때 알파 입자($^4He$ 원자)가 형성되는 현상을 이용한 연령측정법이다. 모 동위원소인 $^{238}U$, $^{235}U$ 및 $^{232}Th$과 붕괴산물인 $^4He$의 양을 측정하여 (U-Th)/He 연령을 구할 수 있다. 이렇게 형성된 $^4He$ 원자는 대부분의 지질학적 시료내에서 비교적 저온에서도 빠르게 확산되는데, 이는 $^4He$가 불활성 기체이고 다른 원소에 비해 작기 때문이다. 따라서 방사성 붕괴에 의한 $^4He$의 형성(ingrowth)과 확산에 의한 $^4He$의 방출(diffusive loss)이 지질학적 시간동안 어떻게 진행 되었느냐에 따라 현재 남아있는 $^4He$의 양이 결정된다. 예를 들어, 인회석내에서의 He 확산은 다른 광물에 비해 빨라서, 비교적 저온인 $80^{\circ}C$에서도 He이 빠르게 인회석 밖으로 방출되는 것으로 알려져 있다. 자연상의 온도조건이 약 $40^{\circ}C$ 이하로 떨어졌을 때 비로소 인회석내 He 확산이 충분히 느려져서 대부분의 He이 인회석내에 보존된다. 따라서 (U-Th)/He 연령은 시료가 $80-40^{\circ}C$를 통과한 시기를 지시한다. 자연상에서 이러한 온도범위에 해당하는 깊이를 "부분 보존대"(partial retention zone)의라 한다. 전통적으로 흔히 쓰이는 폐쇄온도(closure temperature)는 보통의 입자크기와 냉각속도에서, 인회석 경우 약 $60-70^{\circ}C$, 저어콘 및 티탄석의 경우 약 $200^{\circ}C$로 알려져 있다. 특히 인회석의 He 폐쇄온도는 다른 열역사 측정법에 비해 다소 낮기 때문에 비교적 최근의 열역사 또는 천부에서의 지각융기 현상을 기술하는데 매우 유용하게 쓰일 수 있다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2006년도 학술논문요약집
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• pp.35-36
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• 2006

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2016년도 춘계학술논문요약집
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• pp.443-444
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• 2016

• 암석학회지
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• 제10권3호
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• pp.148-156
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• 2001

경북 경주시 인근의 제4기 추정단층 중 입실단층과 장항리단층의 파쇄대를 충진하고 있는 탄산염암맥을 대상으로 다검출기 유도결합 플라즈마 질량분석기를 이용한 $^{230}$ $Th^{234}$ U 비평형 연대를 측정하였다. 완전히 녹인 시료로부터 공침과 이온교환화학을 통해 간편하게 U, Th을 단체분리하였는데 회수율은 Th 80%, U 70% 정도였다. 이 부분으로부터 기기 조건이 최적화된 다검출기 유도결합 플라즈마 질량분석기를 이용하여 $^{234}$ $U^{238}$ $U^{230}$ $Th^{232}$ Th비를 분석하였고 U/Th비는 처리하지 않은 시료로부터 직접 분석하였다. 분석 결과 입실 단층의 탄산염암 맥은 $^{234}$ U-$^{230}$ Th 시차평형에 도달하여 기존의 ESR 연대측정 결과를 지지하였으며 쇄설성 부분이 보정된 장항리단층 탄산염암 맥의 $^{230}$$Th^{234}$ /U 비평형 연대는$ 48\pm$41 ka로서 파쇄대의 최소 형성시기를 지시한다.

• Nuclear Engineering and Technology
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• 제49권8호
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• pp.1752-1757
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• 2017

The aim of this study is to evaluate the radioactivity levels and radiological impacts of representative black sand samples collected from different locations in the Rashid area, Egypt. These samples were prepared and then analyzed using the high-resolution gamma ray spectroscopy technique with a high-purity germanium detector. The activity concentration ($A_c$), minimum detectable activity, absorbed gamma dose rate, external hazard index ($H_{ex}$), annual effective dose rate equivalent, radium equivalent, as well as external and internal hazard index ($H_{ex}$ and $H_{in}$, respectively) were estimated based on the measured radionuclide concentration of the $^{238}U$($^{226}Ra$) and $^{232}Th$ decay chains and $^{40}K$. The activity concentrations of the $^{238}U$, $^{232}Th$ decay series and $^{40}K$ of these samples varied from $45.11{\pm}3.1Bq/kg$ to $252.38{\pm}34.3Bq/kg$, from $64.65{\pm}6.1Bq/kg$ to $579.84{\pm}53.1Bq/kg$, and from $403.36{\pm}20.8Bq/kg$ to $527.47{\pm}23.1Bq/kg$, respectively. The activity concentration of $^{232}Th$ in Sample 1 has the highest value compared to the other samples; this value is also higher than the worldwide mean range as reported by UNSCEAR 2000. The total absorbed gamma dose rate and the annual effective dose for these samples were found to vary from 81.19 nGy/h to 497.81 nGy/h and from $99.86{\mu}Sv/y$ to $612.31{\mu}Sv/y$, which are higher than the world average values of 59 nGy/h and $70{\mu}Sv/y$, respectively. The $H_{ex}$ values were also calculated to be 3.02, 0.47, 0.63, 0.87, 0.87, 0.51 and 0.91. It was found that the calculated value of $H_{ex}$ for Sample 1 is significantly higher than the international acceptable limit of <1. The results are tabulated, depicted, and discussed within national and international frameworks, levels, and approaches.

• 분석과학
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• 제30권5호
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• pp.262-269
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• 2017

금강수계 하천 및 호소 퇴적물에 대하여 천연 방사성핵종 농도를 조사하였다. 조사의 대상이 되는 지점은 하천 17 개 지점, 호소 6 개 지점으로 총 23 개 지점이며, 하천은 2015년 9월부터 11월, 호소는 2015년 3월부터 4월까지 시료를 채취하였다. 분석 대상 핵종은 $^{226}Ra$ 계열, $^{232}Th$ 계열과 $^{40}K$ 핵종이며, 고순도 게르마늄 검출기(HPGe)를 이용하여 대상 핵종 또는 그 자핵종이 방출하는 감마선을 계측하였다. 분석 결과 하천 퇴적물 중 $^{226}Ra$계열, $^{232}Th$ 계열과 $^{40}K$의 방사성핵종 농도는 각각 $15.6{\pm}0.6$, $33.8{\pm}1.2$, $789.8{\pm}26.0Bq/kg$ 으로 나타났으며, 호소 퇴적물의 농도는 각각 $17.0{\pm}0.5$, $37.8{\pm}1.1$, $269.4{\pm}9.6Bq/kg$으로 나타났다. $^{232}Th$ 계열 방사성핵종의 농도는 퇴적물 입도와 연관성을 보였으며, 핵종의 이동 특성에 따라 $^{226}Ra$ 계열보다 높게 나타났다. $^{40}K$의 농도는 퇴적물 중 유기물 함량과 관련을 보였으며, 하천에 비하여 호소에서 낮은 농도로 조사되었다.