• Nuclear Engineering and Technology
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• 제55권8호
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• pp.2802-2811
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• 2023

In a first-of-its-kind study, terrestrial radionuclide concentrations were measured in 35 topsoil samples from the outskirts of Dhaka using HPGe gamma-ray spectrometry to assess the radiological consequences of such a vast number of brick kilns on the plant workers, general as well as dwelling environment. The range of activity concentrations of ²²⁶Ra, ²³²Th, and ⁴⁰K is found at 19 ± 3.04 to 38 ± 4.94, 39 ± 5.85 to 57 ± 7.41, and (430 ± 51.60 to 570 ± 68.40) Bq/kg, respectively. ²³²Th and ⁴⁰K concentrations were higher than the global averages. Bottom ash deposition in lowlands, fly ash buildup in soils, and the fallout of micro-particles are all probable causes of the elevated radioactivity levels. ¹³⁷Cs was found in the sample, which indicates the migration of ¹³⁷Cs from nuclear accidents or nuclear fallout, or the contamination of feed coal. Although the effective dose received by the general public was below the recommended dose limit but, most estimates of hazard parameters surpass their respective population weighted global averages, indicating that brick kiln workers and nearby residents are not safe due to prolonged exposures to terrestrial radiation. In addition, the soil around sampling sites is found to be unsuitable for agricultural purposes.

• 한국식품위생안전성학회지
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• 제36권3호
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• pp.248-256
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• 2021

건조 수산가공식품의 안전성 확보를 위해 2020년 경기도 내 유통 중인 건조 수산가공식품 12품목 120건을 수거하여 방사능(¹³¹I, ¹³⁴Cs, ¹³⁷Cs) 및 중금속(납, 카드뮴, 비소, 수은) 함량을 분석하였다. 모든 시료에서 자연 방사성 핵종 중 하나인 ⁴⁰K만 검출되었으며, 인공 방사성 물질인 ¹³¹I, ¹³⁴Cs, ¹³⁷Cs는 최소검출가능농도(MDA) 이하의 값을 나타내었다. 중금속의 평균 함량[평균±표준편차(최소값-최대값)]은 생물로 환산하였을 때 납 0.066±0.065(N.D.-0.332) mg/kg, 카드뮴 0.200±0.406(N.D.-2.941) mg/kg, 비소 3.630±3.170(0.371-15.007) mg/kg, 수은 0.009±0.011(0.0005-0.0621) mg/kg 이었으며, 수산물에서 중금속 기준이 있는 제품의 경우 모두 기준 규격 이내로 나타났다. 국내산 제품과 수입산 제품의 중금속 함량은, 조개의 카드뮴과 새우의 수은 함량에서만 유의적인 차이를 나타내었다(P<0.05). 본 연구 결과, 유통 중인 건조 수산가공식품에서 방사능 및 중금속은 안전한 수준인 것으로 판단되나, 식품 중 특히 수산물에서 방사능 오염에 대한 국민의 우려가 크기 때문에 국민들의 불안감 해소를 위해 방사능 검사는 지속적으로 필요할 것으로 생각된다. 또 향후 건조 수산가공식품 중에서도 건조된 형태로 직접 섭취 가능한 제품의 중금속 관리 기준 설정을 위한 기초 자료로 활용할 수 있을 것이다.

• Journal of Radiation Protection and Research
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• 제48권2호
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• pp.84-89
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• 2023

Background: Food consumption is one of the most important routes for radionuclide intake for the public; therefore, there is the need to have a comprehensive understanding of the amount of radioactivity in food products. Consumption of radionuclide-contaminated food could increase potential health risks associated with exposure to radiation such as cancers. The present study aims to determine radioactivity levels in some food products (milk, rice, sugar, and wheat flour) consumed in Mali and to evaluate the radiological effect on the public health from these radionuclides. Materials and Methods: The health impact due to ingestion of radionuclides from these foods was evaluated by the determination of activity concentration of radionuclides ²³⁸U, ²³²Th, ⁴⁰K, and ¹³⁷Cs using gamma spectrometry system with high-purity germanium detector and radiological hazards index in 16 samples collected in some markets, mall, and shops of Bamako-Mali. Results and Discussion: The average activity concentrations were 9.8±0.6 Bq/kg for ²³⁸U, 8.7±0.5 Bq/kg for ²³²Th, 162.9±7.9 Bq/kg for ⁴⁰K, and 0.0035±0.0005 Bq/kg for ¹³⁷Cs. The mean values of radiological hazard parameters such as annual committed effective dose, internal hazard index, and risk assessment from this work were within the dose criteria limits given by international organizations (International Commission on Radiological Protection and United Nations Scientific Committee on the Effects of Atomic Radiation) and national standards. Conclusion: The results show low public exposure to radioactivity and associated radiological impact on public health. Nevertheless, this study stipulates vital data for future research and regulatory authorities in Mali.

• Nuclear Engineering and Technology
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• 제51권8호
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• pp.1991-1997
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• 2019

In this manuscript, we present a method for the direct calculation of an ambient dose equivalent (H^* (10)) for the external gamma-ray exposure with an energy range of 40 keV to 2 MeV in an electronic personal dosimeter (EPD). The designed EPD consists of a 3 × 3 ㎟ PIN diode coupled to a 3 × 3 × 3 ㎣ CsI (Tl) scintillator block. The spectrum-to-dose conversion function (G(E)) for estimating H^* (10) was calculated by applying the gradient-descent method based on the Monte-Carlo simulation. The optimal parameters for the G(E) were found and this conversion of the H^* (10) from the gamma spectra was verified by using ²⁴¹Am, ¹³⁷Cs, ²²Na, ⁵⁴Mn, and ⁶⁰Co radioisotopes. Furthermore, gamma spectra and H^* (10) were obtained for an arbitrarily mixed multiple isotope case through Monte-Carlo simulation in order to expand the verification to more general cases. The H^* (10) based on the G(E) function for the gamma spectra was then compared with H^* (10) calculated by simulation. The relative difference of H^* (10) from various single-source spectra was in the range of ±2.89%, and the relative difference of H^* (10) for a multiple isotope case was in the range of ±5.56%.

• Nuclear Engineering and Technology
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• 제42권1호
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• pp.89-96
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• 2010

This paper describes the methodology of calculating the internal dose conversion coefficient in order to assess the radiological impact on non-human species. This paper also presents the internal dose conversion coefficients of 25 radionuclides ($^3H,\;^7Be,\;^{14}C,\;^{40}K,\;^{51}Cr,\;^{54}Mn,\;^{59}Fe,\;^{58}Co,\;^{60}Co,\;^{65}Zn,\;^{90}Sr,\;^{95}Nb,\;^{99}Tc,\;^{106}Ru,\;^{129}I,\;^{131}I,\;^{136}Cs,\;^{137}Cs,\;^{140}Ba,\;^{140}La,\;^{144}Ce,\;^{238}U,\;^{239}Pu,\;^{240}Pu$) for domestic seven reference animals (roe deer, rat, frog, snake, Chinese minnow, bee, and earthworm) and one reference plant (pine tree). The uniform isotropic model was applied in order to calculate the internal dose conversion coefficients. The calculated internal dose conversion coefficient (${\mu}Gyd^{-1}$ per $Bqkg^{-1}$) ranged from $10^{-6}$ to $10^{-2}$ according to the type of radionuclides and organisms studied. It turns out that the internal does conversion coefficient was higher for alpha radionuclides, such as $^{238}U,\;^{239}Pu$, and $^{240}Pu$, and for large organisms, such as roe deer and pine tree. The internal dose conversion coefficients of $^{239}U,\;^{240}Pu,\;^{238}U,\;^{14}C,\;^3H$, and $^{99}Tc$ were independent of the organism.

• 한국환경과학회지
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• 제24권3호
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• pp.275-280
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• 2015

In order to measure the Radionuclides and Concentration, the directly grinded land samples (river soil, pine leaves and mugwort) among the environment samples around the nuclear power plant were filled in a 450 mL Marinelli beaker and weighed to obtain the dry mass ratio of the samples. Then the background and land samples were measured for 80,000 sec. The analysis of the collected land samples showed that most of them contained less radiation nuclide than the detection minimum limit in the 'Ministry of Education, Science and Technology Public Notice No. 2010-32.'In others, the natural radionuclides $^{40}K$ were detected. Of the products of nuclear reaction discharged by a nuclear reaction, $^{134}Cs$ and $^{137}Cs$ are more easily detected, and their discharge sources can be traced using the relative ratio. Although the radioactive concentration in the vicinity of Kori Nuclear Power Plant, which is more than 1,100km away from Fukushima, the Japanese nuclear accident site, continuous monitoring is needed as the radionuclides can still be accumulated in the soil or animals and plants.

• Journal of Radiation Protection and Research
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• 제41권2호
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• pp.179-183
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• 2016

Background: As an important detecting device, TLD is a widely used in the radiation monitoring. It is essential for us to study the property of detecting element. The aim of this study is to calculate the thermo-luminescence efficiency of TL elements. Materials and Methods: A batch of thermo-luminescence elements were irradiated by the filtered X-ray beams of average energies in the range 40-200 kVp, 662 keV $^{137}Cs$ gamma rays and then the amounts of lights were measured by the TL reader. The deposition energies in elements were calculated by theory formula and Monte Carlo simulation. The unit absorbed dose in elements by photons with different energies corresponding to the amounts of lights was calculated, which is called the thermo luminescent efficiency (${\eta}^{(E)}$). Because of the amounts of lights can be calculated by the absorbed dose in elements multiply ${\eta}^{(E)}$, the ${\eta}^{(E)}$ can be calculated by the experimental data (the amounts of lights) divided by absorbed dose. Results and Discussion: The deviation of simulation results compared with theoretical calculation results were less than 5%, so the absorbed dose in elements was calculated by simulation results in here. The change range of ${\eta}^{(E)}$ value, relative to 662 keV $^{137}Cs$ gamma rays, is about 30% in the energy range of 33 keV to 662 keV, is in accordance by the comparison with relevant foreign literatures. Conclusion: The ${\eta}^{(E)}$ values can be used for updating the amounts of lights that are got by the direct ratio assumed relations with deposition energy in TL elements, which can largely reduce the error of calculation results of the amounts of lights. These data can be used for the design of individual dosimeter which used TLD-2000 thermo-luminescence elements, also have a certain reference value for manufacturer to improve the energy-response performance of TL elements by formulation adjustment.

• Radiation Oncology Journal
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• 제3권2호
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• pp.95-101
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• 1985

1979년 7월부터 1985년 3철까지 한양대학병원에서 자궁경암의 표준화된 방사선치료기준, 즉 전 골반의 외부방사선조사와 강내조사의 병용요법으로 112명의 환자를 치료하였다. 전원이 추적 가능하였고 $6\~75$개월의 추적기간에 평균은 31개월이었다. 2명이 선암이고 110명은 펀평상피 세포암이었고 $I_b$병기 9명$(8\%)$, $II_a$병기 14명$(12.5\%)$, $II_b$ 병기 50명$(44.6\%)$, III병기 33명 $(29.5\%)$, 그리고 IV병기는 6명 $(5.4\%)$이었다. 연령분포는 30대 10명$(8.9\%)$, 40대, 50대가 다같이 41명$(36.6\%)$씩으로 $73.2\%$이고 60대 이상이 19명 $(17\%)$이며 특수하게 20세미만이 1예 있었다. 방사선치료는 전 골반에 평행대항 조사야로 $180\~200rad$를 주 5회 $4,000\~4,200rad$ 조사하였고 중앙부 4cm를 차폐하고 $600\~l,000rad$를 자궁방결합조직에 추가 조사하였다. 강내조사는 Cs-137 소선원(20mg 라디움당량)을 자궁강내 $2\~3$개 질강내 2개를 TAO Applicator로 삽입하였고 $7\~12$일 간격으로 2회 시행하였다. 치료기간은 평균 52일간이고 $40\~65$일에 걸쳐서 시행되었다. A점에 조사한 방사선량은 $6,820\~10,500rad$로 평균 8,388rad이고 B점에는 $4,850\~6,899rad$로 평균 5,898rad이었다. 생명표 5년 생존율(actuarial 5year survival rate)은 전체로 $61.8\%$이고, $I_b$병기에서 $84.6\%$, $II_a$병기는 $77.8\%$, $II_b$병기는 $56.7\%$, III병기는 $60.6\%$, 그리고 IV 병기는 $33.3\%$이었다. A점의 방사선량이 8,000rad 이상일 때는 7/18$(38.9\%)$의 실패율이었고 이에 비해서 8,000rad이상일 때는 25/94$(26.5\%)$의 실패율이었다. 또 B점 선량으로 보면 6,000rad이하에서 20/63$(34.9\%)$의 실패율에 비하여 6,000rad이상일 때는 10/49$(20.4\%)$의 실패율이었다. 연령 벨로는 $40\~49$세에서 실패율(14/41 $24.1\%$)이 많았다. 본 성적으로 보아서 생존율은 여러 저자들과 큰 차이가 없음을 알 수 있었고 A점 선량은 8,000rad 이상, B점은 6,000rad이상이 조사되어야 적정선량이 됨을 시사해 주고 있다.

• 한국토양비료학회지
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• 제41권2호
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• pp.137-142
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• 2008

This study was conducted to evaluate the humification grade of compost, based on physico-chemical property and phyto-toxicity during the composting with three kinds of livestock manures and saw dust. The ratios of the compost, which was mixed with pig manure(P) and sawdust(S) were 4 : 6(PS-1), 5 : 5(PS-2) and 6 : 4(PS-3); poultry manure(PO) and sawdust(S) were 4 : 6(POS-1), 5 : 5(POS-2) and 6 : 4(POS-3); cow manure(C) and sawdust(S) were 4 : 6(CS-1), 5 : 5(CS-2) and 6 : 4(CS-3) by volume to volume, and they were decomposed for 60 days. In the result, the temperature in all treatments during composting rapidly increased above $65.4^{\circ}C$, and then gradually decreased to around $40^{\circ}C$. At 60 day, after the treatment, pH 5.9 ~ 8.0 at the incipient stage increased to 7.6 ~ 8.5, and the C/N ratio was 13.8 ~ 21.1 at the final composting stage. Germination Index(G.I.) showed in the range of 75.1 ~ 94.6 in all treatments at day 60. Therefore, it is likely recommended to take the best humification grade when the temperature maintains above $65^{\circ}C$ longer than a day at minimum, in the range of pH 6.5 ~ 8.5 for the final compost, under 20 of C/N ratio, and G.I. above 80. The level of G.I. above 80 should be the mature compost which could be used in the field without gas demage to crops.

• Journal of Radiation Protection and Research
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• 제31권1호
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• pp.1-7
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• 2006

The measured mean activities of $^{226}Ra,\;^{232}Th,\;^{40}K\;and\;^{137}Cs$ in the soil of Bahawalpur, Bahawalnagar and Rahimyar Khan Bistricts were 32.9, 53.6, 647.4 and 1.8 Bq $kg^{-1}$. The average absorbed dose rate calculated from these activities was 74.3 nGy $h^{-1}$ and the mean annual effective dose rate was found to be 0.46 mSv $y^{-1}$. Absorbed doses to different body organs were derived from annual effective doses using tissue weighting factors. Radiation induced fatal cancer risks were assessed by using ICRP 60 Model. Estimations incurred 184deaths per year due to cancer.