• Title/Summary/Keyword: BQ Analysis

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Evaluation and Consideration on Environmental Radiation Analysis of Yeong-Gwang Nuclear Power Plant Site Inside&Outside(2000~2009 year) (영광원전 부지 내.외부의 환경방사능 분석에 대한 평가 및 고찰(2000~2009년))

  • Han, Sang-Jun;Lee, Seung-Jin;Lee, Goung-Jin;Lee, Na-Young;Kim, Hee-Gang;Mun, Ji-Yeon
    • Journal of Radiation Protection and Research
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    • v.36 no.2
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    • pp.71-78
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    • 2011
  • Yeong-Gwang N.P.P Private Environment Supervisory Organization analyzed over 3,000 samples including 10 marine and 24 land samples from the year 2,000 to 2009. According to the results of the analysis, artificial nuclides that resulted from the effect of Yeong-Gwang Nuclear Power Plant operations were not detected in most samples. However, from the rain and seawater samples, which were taken from inside the plants such as the intake, the discharge and the observatory, $^3H$ was detected although it was below the regulation level. The $^3H$ concentration detected in the rain taken from the observatory, by the yearly average criterion, was 30.5~40.0 $Bq{\cdot}L^{-1}$, which is around 20 times the $^3H$ concentration detected in the surroundings of the power plants, but it is 0.1% of the regulation level of 40,000 $Bq{\cdot}L^{-1}$. Also, $^3H$ concentration detected in the seawater taken from the intake and the discharge, by the yearly average criterion, was 2.75~17.8$Bq{\cdot}L^{-1}$, which means the concentration detected in the discharge is about 140~280% higher than that detected in the intake except the year 2006. Based on these results, it was determined that, although lower than the regulation level, the $^3H$ in gas and liquid form detected in the rain and seawater sampled from the observatory and the discharge was released into the environment from the power plants. Therefore, regular monitoring and analysis is required on the level of $^3H$ in the observatory and the discharge.

Analysis of $^{99}Tc$ and Its Activity Level in the Korean Soil (한국 토양의 $^{99}Tc$ 분석 및 방사능 농도 준위)

  • Lee, Chang-Woo;Chung, Kun-Ho;Cho, Young-Hyun;Kang, Mun-Ja;Lee, Wan-No;Kim, Hee-Reyoung;Choi, Geun-Sik
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.7 no.1
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    • pp.25-31
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    • 2009
  • An analytical method of $^{99}Tc$ concentration in soil was set up and discussed considering the $^{99}Tc$ concentration in Korean soil measured with its analytical method. A selective TEVA resin was used to separate and purify the $^{99}Tc$ in the soil sample. $^{99m}Tc$ from a commercial $^{99}Mo/^{99m}Tc$ generator was used as a yield tracer for the chemical separation of $^{99}Tc$ and its problem when using $^{99m}Tc$ as a tracer was discussed. The chemical recovery yield of $^{99}Tc$ was above 70%. The optimum conditions of inductively coupled plasma mass spectrometry system(ICP-MS) were set up to determine the $^{99}Tc$ after the separation process. The minimum detectable activity(MDA) was 15 mBq/kg-dry in this analytical procedure. The $^{99}Tc$ concentration in soils of Jeju and Kori were measured in the rage of 33.73-89.16 mBq/kg-dry. Those values were less than those reported in other countries and seemed to be originated from atmospheric fallout.

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Analysis of Uranium Concentrations in Urine Samples Using Alpha Spectrometry and Dose Assessment (알파분광분석법을 이용한 소변시료 중 우라늄 농도 분석 및 선량평가)

  • Lee, Na-Rae;Han, Seung-Jae;Cho, Kun-Woo;Jeong, Kyu-Hwan;Lee, Dong-Myung
    • Journal of Radiation Protection and Research
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    • v.38 no.3
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    • pp.138-142
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    • 2013
  • This study was conducted to measure the uranium concentrations in urine of some members of the general public in Busan and Daejeon and to assess the annual committed effective doses from uranium analysis of daily excretion. As a result, the ranges of total uranium concentrations in the urine for the residents in Busan and Daejeon were found to be 0.556 - 1.53 $mBq\;L^{-1}$ and 2.18 - 4.55 $mBq\;L^{-1}$, respectively. It was noted that the uranium concentrations for the residents in Daejeon were observed to be higher than those for the residents in Busan. This result assumes that the uranium concentrations in the urines for the residents in Daejeon are probably related to the high uranium concentrations contained in the drinking water of Daejeon city. The bedrock of Daejeon, known as granitic rocks formed in the Jurassic period of the Mesozoic Era, contains high uranium contents. Also, results showed no significant correlation with age or sex. The ranges of annual committed effective doses from ingestion of uranium for the residents in Busan and Daejeon were calculated to be 0.472-1.41 ${\mu}Sv$ and 1.99-4.15 ${\mu}Sv$, respectively.

Assessment of radioactivity levels and radiation hazards in building materials in Egypt

  • Ahmed E. Abdel Gawad;Mohamed Y. Hanfi;Mostafa N. Tawfik;Mohammed S. Alqahtani;Hamed I. Mira
    • Nuclear Engineering and Technology
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    • v.56 no.2
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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.

Locational Analysis and Classification of the Eup-Settlements in the Joseon Dynasty Period from Feng-Shui's Point of View (조선시대 지방도시의 풍수적 입지분석과 경관유형- 경상도 71개 읍치를 대상으로 -)

  • Choi, Won-Suk
    • Journal of the Korean Geographical Society
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    • v.42 no.4
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    • pp.540-559
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    • 2007
  • The purpose of this paper is to analyse the locations and to interpret the landscapes of the local towns in Joseon Dynasty from Feng-shui's point of view. As a result of analysing the locations of towns in Gyeongsang Province, the towns which have typical Feng-shui landscapes make up to 58% of the total. Historically, the local towns that were established in the early period of the Joseon Dynasty didn't reveal Feng-shui's landscape, but those that were established in the late period of the Joseon Dynasty revealed the Feng-shui's landscape clearly. In this article, I classify the local towns of the Gyeongsang Province into 3 types: 1. Non Feng-shui type These towns are located near the seashore. The main reason that these towns were located at the seashore was defense against an enemy. 2. Semi Feng-shui type. These towns don't have natural location but have a man-made landscape, based on the principles of Feng-shui. 3. Typical Feng-shui type. These towns were typically administrational towns which were located at the center of a local region.

An analysis of the concentration of radioactivity of natural radionuclides (238U, 232Th, 40K) and gamma-ray emitting artificial radionuclides(137Cs, 60Co) present in the drinking water of the city of Busan, Republic of Korea, and the calculated absorbed dose of the residents

  • Kim, Chang-Soo;Kim, Jung-Hoon
    • International Journal of Contents
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    • v.8 no.2
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    • pp.60-66
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    • 2012
  • This study was designed to detect and measure the concentration of radioactivity of natural radionuclides ($^{238}U$, $^{232}Th$, $^{40}K$) and artificial radionuclides ($^{137}Cs$, $^{60}Co$) present in the drinking water of the city of Busan and surrounding areas in South Korea, and also to measure the absorbed dose of radiation caused by these elements in the residents so as to help better manage the risk that these radionuclides pose in the future. For the purposes of the study, a total of 42 samples of water were collected from three key water sources (19 samples of groundwater, 4 samples of tap water, and 19 samples of surface water) and their contents were analyzed for radioactivity concentration. The results revealed that two natural radionuclides, $^{238}U$ and $^{232}Th$, exist in the groundwater with an average concentration of radioactivity of 3.34 Bq/L and $8.28{\times}10^{-5}Bq/L$ respectively, while the surface water was found to contain the same two radionuclides with mean concentrations of 0.849 Bq/L and $1.103{\times}10^{-4}Bq/L$ respectively. In addition, of the 19 samples of the groundwater, $^{137}Cs$ was found in eight of them and $^{60}Co$ was detected in ten. Of the four samples of the tap water, $^{137}Cs$ was detected in all samples and $^{60}Co$ was detected in three. Both $^{137}Cs$ and $^{60}Co$ were detected in all 12 samples of surface water. As far as $^{40}K$ is concerned, this element was detected in three of the 19 groundwater samples, but was not detected in any surface or tap water sample. In addition, the absorbed dose of $^{238}U$ from the groundwater was $7.94{\times}10^{-8}Sv/y$, while the absorbed dose of $^{232}Th$ from the surface water was $9.33{\times}10^{-13}Sv/y$. The absorbed dose of $^{137}Cs$ from the tap water was $7.33{\times}10^{-5}Sv/y$, while the absorbed dose of $^{60}Co$ from the surface water was the highest at $4.23{\times}10^{-6}Sv/y$.

Radioactivity Analysis of Soils Stored in KAERI for Regulatory Clearance (연구소 내 저장 중인 토양의 규제해제를 위한 방사능 분석)

  • Hong D.S.;Kim T.K.;Kang I.S.;Cho H.S.;Shon J.S.
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2005.06a
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    • pp.161-166
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    • 2005
  • In KAERI, about 3,100 drums containing soil have been stored. The soils were generated from the decommissioning process of Seoul office in 1988. Those soils occupy about $27\%$ of the capacity of the radioactive waste storage facility and make it difficult to maintain the storage facility. The major radioactive nuclides contained in the soils were expected to be Co-60 and Cs-137. As 16 years have passed, the radioactivity of those nuclides have decayed a lot. In this study, as a basis of regulatory clearance, radionuclides and radioactivity concentration of soils were analyzed. As a result, there are only Co-60 and Cs-137 in soils as ${\gamma}-emitters$. The total concentration of ${\gamma}-emitters$ in soil is analyzed as about $0.01\;{\sim}\;0.12$ Bq/g. As the soils are expected to be regulatory cleared in 2009, those concentrations will decay to be less than 0.1 Bq/g. This concentration can be meet the regulatory criteria suggested by IAEA. The regulatory clearance will be proceeded based on not only the assessment results of environmental influence but also related regulations.

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Analysis of 226Ra in the Groundwater Using the Gamma-ray Spectroscopy (감마선 분광법을 이용한 지하수 중의 226Ra 분석)

  • Seo, Bum-Kyoung;Lee, Kil-Yong;Yoon, Yoon-Yeol;Lee, Kune-Woo
    • Analytical Science and Technology
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    • v.16 no.1
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    • pp.39-47
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    • 2003
  • The measurement of radium ($^{226}Ra$) in the groundwater was established using ${\gamma}$-ray spectroscopy without sample preparation. The background interference by air borne radon daughter nuclides was reduced by $N_2$ gas flow into the counting chamber. Leakage of radon gas produced in the radioactive equilibrium with radium and its daughter nuclides was prevented by use of the air-tighted aluminium container. We investigated the effect of air layer in the counting container. Radioactivity variation due to emanation of radon into the air layer was within the counting error range 5%. When the nitrogen gas was flowed around the detector, peak counts of ${\gamma}$-rays from the daughters of airborne radon was decreased and detection limit was decreased to 0.02 Bq/L. The detection limit of detector was lower than 0.74 Bq/L, the $^{226}Ra$ Maximum Contaminant Level (MCL) in the groundwater proposed by US Environmental Protection Agency (EPA). It was confirmed that $^{226}Ra$ radioactivity in the groundwater could be determined by the ${\gamma}$-ray spectroscopy.

A Study on the Decontamination of Cs-137 and Sr-90 Contained in the Liquid Radioactive Waste Discharged from the Spent Fuel Storage Tank Using Microalgae (미세조류를 이용한 사용후핵연료 저장조에서 배출되는 방사성 폐액에 함유된 Cs-137 및 Sr-90 제염에 관한 연구)

  • Kim, Tae Young;Park, Hye Min;Song, Yang Soo;Lee, Un Jang
    • Resources Recycling
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    • v.31 no.5
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    • pp.20-25
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    • 2022
  • In this study, the applicability of microalgae was evaluated for eco-friendly decontamination of cesium-137 (Cs-137) and strontium-90 (Sr-90), which are radioactive nuclides contained in radioactive waste. The monolithic radioactive solution used in the experiment was manufactured at a concentration of 1.5 Bq/mL Cs-137 and 1.0 Bq/mL Sr-90 by diluting a standard radioactive solution and distilled water. This experiment used two types of microalgae, Chlorella Vulgaris was used for Sr-90 decontamination and Hematococcus pluvialis for Cs-137 decontamination. The experimental method is to put the microalgae cultured for 2 weeks into a bottle with a semi-permeable membrane, and then put the bottle in which the microalgae was put into the manufactured radioactive solution, so that the microalgae and the radioactive solution react through the semi-permeable membrane for 48 hours. For the radioactivity concentration analysis of each sample, a gamma-ray nuclide analyzer was used for Cs-137, a γ-ray isotope, and a Liquid Scintillation Count(LSC) was used f or Sr-90, a β-ray isotope. As a result of the experiment, it was confirmed that about 88.0 % of Cs-137 and about 89.7 % of Sr-90 could be decontaminated, and about 98.6 % of Sr-90 was finally able to be decontaminated by the two-stage decontamination method.

Comparative Study of Tritium Analysis Method with High-Volume Counting Vial

  • Yoon, Yoon Yeol;Kim, Yongcheol
    • Journal of Radiation Protection and Research
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    • v.45 no.3
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    • pp.142-146
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    • 2020
  • Background: Tritium (3H) analysis in groundwater was difficult because of its low activity. Therefore, the electrolytic enrichment method was used. To improve the detection limit and for performing simple analysis, a high-volume counting vial with the available liquid scintillation counter (LSC) was investigated. Further, it was compared with a conventional 20-mL counting vial. Materials and Methods: The LSC with the electrolytic enrichment method was used 3H analysis in groundwater. A high-volume 145-mL counting vial was compared with a conventional 20-mL counting vial to determine the counting characteristics of different LSCs. Results and Discussion: When a Quantulus LSC was used, the counting window between channels 35 and 250 was used. The background count was approximately 1.86 cpm, and the counting efficiency increased from 8% to 40% depending on the mixing ratio of the volume of sample and cocktail solution. For LSC-LB7, the optimum counting window was between 1 and 4.9 keV, which was selected by the factory (Hitachi Aloka Medical Ltd., Japan) by considering quenching using a standard external gamma source. The background count of LSC-LB7 was approximately 3.60 ± 0.29 cpm when the 145-mL vial was used and 2.22 ± 0.17 cpm when the 20-mL vial was used. The minimum detectable activity (MDA) of the 20-mL vial was greater for LSC-LB7 than for Quantulus. The MDA with the 145-mL vial was improved to 0.3 Bq/L when compared with the value of 1.6 Bq/L for the 20-mL vial. Conclusion: The counting efficiency when using the 145-mL vial was 27%, whereas it was 18% when using the 20-mL vial. This difference can be attributed to the vial volume. The figure of merit (FOM) of the 145-mL vial was four times greater than that of the 20-mL vial because the volume of the former vial is approximately seven times greater than that of the latter. Further, the MDA for 3H decreased from 1.6 to 0.3 Bq/L. The counting efficiency and FOM of LSC-LB7 was slightly less than those of Quantulus when the 20-mL vial was used. The background counting rate of the Quantulus was lower than that of the LSC-LB7.