• Nuclear Engineering and Technology
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• 제54권6호
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• pp.2230-2243
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• 2022

The tin tailing processing industry in Malaysia has operated with minimal regard and awareness for material management and working environment safety, impacting the environment and workers in aspects of radiation and heavy metal exposure. RIA was conducted where environmental samples were analyzed, revealing concentrations of ²²⁶Ra, ²³²Th and ⁴⁰K between the range of 0.1-10.0, 0.0-25.7, and 0.1-5.8 Bq/g respectively, resulting in the AED exceeding UNCEAR recommended value and regulation limit enforced by AELB (1 mSv/y). Ra_eq calculated indicates that samples collected pose a significant threat to human health from gamma-ray exposure. Assessment of heavy metal content via pollution indices of soil and sediment showed significant contamination and enrichment from processing activities conducted. As and Fe were two of the highest metals exposed both via soil ingestion with an average of 4.6 × 10^-3 mg/kg-day and 1.4 × 10^-4 mg/kg-day, and dermal contact with an average of 5.6 × 10^-4 mg/kg-day and 6.0 × 10^-4. mg/kg-day respectively. Exposure via accidental ingestion of soil and sediment could potentially cause adverse non-carcinogenic and carcinogenic health effect towards workers in the industry. Correlation analysis indicates the presence of a relationship between the concentration of NORM and trace elements.

• Nuclear Engineering and Technology
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• 제54권11호
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• pp.4253-4264
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• 2022

Since the implementation of the phosphate project in Bled El-Hadba (BEH) deposit, western region of Tébessa, no detailed study has been conducted to assess the natural radioactivity distribution and the associated radiological risk parameter for this open-pit mine. For the sake of determining a credible premining reference database for the region of interest, 21 samples were collected from different geological layers of the above-mentioned deposit. Gamma Spectrometry was applied for measuring radioactivity using a high resolution HPGe semiconductor detector. The obtained activity results have shown a significant broad variation in the radioactive contents for the different phosphate samples. The total average concentrations (in Bq·kg^-1) for ²²⁶Ra, ²³⁸U, ²³⁵U, ²³²Th and ⁴⁰K computed for the different type of phosphate layers were found to be 570 ± 169, 788 ± 280, 52 ± 18, 66 ± 6 and 81 ± 18 respectively. The mean activity concentrations of the measured radionuclides were compared to other regional and worldwide deposits. The ratios between the detected radioisotopes have been calculated for spatial distribution of natural radionuclides in the study area. Based on the aforementioned activity concentrations, the corresponding radiation hazard parameters were assessed. Correlations between the obtained parameters were drawn and a multivariate statistical analysis (Pearson Correlation, Cluster and Factor analysis) was carried out in order to identify the existing relationships.

• 핵의학기술
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• 제15권2호
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• pp.13-20
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• 2011

PET/CT 검사에서 제한적인 CT (Computed Tomography)의 FOV (Field of View)는 PET 영상의 DFOV (Display FOV) 바깥부위에서 영상 잘림 현상 (truncation artifact)에 의한 오류를 유발할 수 있다. 본 논문에서는 영상 재구성 시 확대된 DFOV를 적용함에 따라 PET영상에서 표준섭취계수 (Standardization Uptake Value, SUV)의 차이를 측정하여 영상에 미치는 정도를 비교 평가하고 그 유용성을 알아보고자 하였다. 5.3 kBq/mL의 $^{18}F$(FDG)를 주입한 NEMA 1994 PET 모형을 FOV의 중앙에 위치하고 영상을 획득하고, 동일모형을 FOV의 바깥부분으로 위치를 변경하여 truncation 현상이 발생하도록 한 뒤 같은 방법을 적용하여 영상을 획득하였다. 각 실험을 통해 얻어진 데이터는 동일한 방법을 적용하여 영상을 재구성 하였으며, DFOV는 50 cm와 70 cm로 변경하여 각각 적용하였다. 그리고 방출영상에 관심영역을 설정하고 최대섭취계수($_{max}SUV$)를 비교 하였으며 육안적인 이상유무도 함께 확인하였다. 임상영상은 모형실험에서와 같이 truncation 현상이 발생한 환자군을 선정한 후 해당 환자의 방출영상에서 간(Liver) 부위에 관심영역을 설정하고 모형실험에서와 같이 영상 재구성 시 DFOV 변화에 따른 표준섭취계수의 차이를 비교 하였다. 모형을 FOV 내 중심에 위치시키고 시행한 실험에서 DFOV 증가에 따라 화소의 크기는 3.91 mm에서 5.47 mm로 증가하였고, 관심영역의 $_{max}SUV$는 각각 1.49에서 1.35로 나타나 확대된 DFOV 적용시 9.39%의 감소를 보였다. 모형을 FOV의 바깥부분으로 이동시킨 후 얻은 영상의 경우 $_{max}SUV$가 1.30에서 1.20로 7.69% 감소하였다. DFOV 확대로 인하여 추가적으로 나타난 부위에서의 $_{max}SUV$는 1.51이었고, truncation 현상이 발생한 부위를 기준으로 안쪽과 바깥쪽 부위의 $_{max}SUV$차이는 25.9%로 바깥쪽에서 높은 결과를 보였다. 임상영상의 확대된 DFOV를 적용한 경우 $_{max}SUV$ 3.38에서 3.13으로 7.39% 감소하였다. 확대된 DFOV를 적용할 경우에서의 $_{max}SUV$ 감소 현상은 화소 크기의 증가로 인해 화소 간 잡음 (Pixel to Pixel Noise)이 낮아져 발생하는 저평가 정도의 범위를 벗어나지 않았으며 확대된 부위의 영상에서 육안적 확인 시 선형인공산물 등의 이상이 발견되지 않아 truncation 현상 없는 영상을 얻을 수 있다는 점에서는 임상적 적용이 유용하다고 할 수 있다. 그러나 실제 환자에게 확대된 DFOV를 적용할 경우에는 영상면 전체에서 정량적 결과가 저평가 되는 것을 감안하여야 하며, 특히 확대되어 추가로 나타난 부위에서의 정량적 결과가 높게 나타날 수 있다는 점에 유의하여 적용해야 할 것이다.

• Nuclear Engineering and Technology
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• 제41권5호
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• pp.729-738
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• 2009

Given the evolution of High-Temperature Gas-cooled Reactor(HTGR) designs, the source terms for licensing must be developed. There are three potential source terms: fission products, actinides in the fuel and tritium in the coolant. It is necessary to provide first an inventory of the source terms under normal operations. An analysis of source terms has yet to be performed for HTGRs. The previous code, which can estimate the inventory of the source terms for LWRs, cannot be used for HTGRs because the general data of a typical neutron cross-section and flux has not been developed. Thus, this paper uses a combination of the MCNP, ORIGEN, and MONTETEBURNS codes for an estimation of the source terms. A method in which the HTR-10 core is constructed using the unit lattice of a body-centered cubic is developed for core modeling. Based on this modeling method by MCNP, the generation of fission products, actinides and tritium with an increase in the burnup ratio is simulated. The model developed by MCNP appears feasible through a comparison with models developed in previous studies. Continuous fuel management is divided into five periods for the feeding and discharging of fuel pebbles. This discrete fuel management scheme is employed using the MONTEBURNS code. Finally, the work is investigated for 22 isotope fission products of nuclides, 22 actinides in the core, and tritium in the coolant. The activities are mainly distributed within the range of $10^{15}{\sim}10^{17}$ Bq in the equilibrium core of HTR-10. The results appear to be highly probable, and they would be informative when the spent fuel of HTGRs is taken into account. The tritium inventory in the primary coolant is also taken into account without a helium purification system. This article can lay a foundation for future work on analyses of source terms as a platform for safety assessment in HTGRs.

• 한국도서관정보학회지
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• 제3권
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• pp.89-109
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• 1976

In modern times, it has been a most imporant problem for the community to make nation's information resources a\-ailable to all the people ~vithf ree and even access. In Nelson Associate's National platz for library service appeared in 1948, 50 million Americans were served by public libraries with inadequate service and 35 million have had no library service. Library Services Act signed bq- President Eisenhower in 1956 was a result of continuous efforts of AL.1 for 20 years. It aimed to extend public library service to rural population less than ten thousands. LSA was succeeded by LSCA in 1964 and continued with several amendments so far. 620 million dollars of Federal funds were put into local library administrati1.e agencies during 1957-1974 for the extension of library service and construction of library buildings. Federal funds also encouraged local library administrative agencies to ha\-e more interest in library and information service and carry out their own library programs. However, there are many current problems in Amierican pubic libraries still now, that is, uneven growth of public libraries, uneven distribution of information resources, inadequate library service to a large part of population, insufficient supply of library funds, lack of nationwide library network beyond local admini-strative jurisdictions and so on. National Advisory Commission on Libraries, Committee on Libraries, National Conference of Library and Inforination Science are results of government efforts to meet those problems and carry out effecti1.e nation's library policies. In other part, Congress authorized to open the White House Conference on Library and Information Science before 1978 to make a reco:nn:endation fostering the library use. It is expected that the elected President Carter will put more efforts in developing library and information services, for LSA and LSCA were mainly pushed ahead by Democratic Party. In conclusion I could find some factors through these analysis that would be of some help to develop nation's library and information services, especially in developing countries.

• Nuclear Engineering and Technology
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• 제53권12호
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• pp.4137-4141
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• 2021

As NPPs continue to operate, liquid waste continues to be generated, and containers are needed to store and transport them at low cost and high capacity. To transport and store liquid phase very low-level radioactive waste (VLLW), a container is designed by considering related regulations. The design was constructed based on the existing container design, which easily transports and stores liquid waste. The radiation shielding calculation was performed according to the composition change of barium sulfate (BaSO₄) using the Monte Carlo N-Particle (MCNP) code. High-density polyethylene (HDPE) without mixing the additional BaSO₄, represented the maximum dose of 1.03 mSv/hr (<2 mSv/hr) and 0.048 mSv/hr (<0.1 mSv/hr) at the surface of the inner container and at 2 m away from the surface, respectively, for a 10 Bq/g of ⁶⁰Co source. It was confirmed that the dose from the inner container with the VLLW content satisfied the domestic dose standard both on the surface of the container and 2 m from the surface. Although it satisfies the dose standard without adding BaSO₄, a shielding material, the inner container was designed with BaSO₄ added to increase radiation safety.

• Geomechanics and Engineering
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• 제36권1호
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• pp.51-69
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• 2024

Currently, composite lining mountain tunnels in China are generally classified based on the [BQ] method for the surrounding rock grade. Increasingly, tunnel field construction is replicated indoors for scale down model tests. However, the development of analogous materials for model tests of composite lining tunnels with different surrounding rock grades is still unclear. In this study, typical Class III and V surrounding rock analogous materials and corresponding composite lining support materials were developed. The whole processes of excavation-support dynamics of the mountain tunnels were simulated. Data on the variation of deformations, contact pressures and strains on the surrounding rock were obtained. Finally, a comparative analysis between model tests and numerical simulations was performed to verify the rationality of analogous material development. The following useful conclusions were obtained by analyzing the data from the tests. The main analogous materials of Class III surrounding rock are barite powder, high-strength gypsum and quartz sand with fly ash, quartz sand, anhydrous ethanol and rosin for Class V surrounding rock. Analogous materials for rockbolts, steel arches are replaced by aluminum bar and iron bar respectively with both shotcrete and secondary lining corresponding to gypsum and water. In addition, load release rate of Class V surrounding rock should be less than Class III surrounding rock. The fenestration level had large influence on the load sharing ratio of the secondary lining, with a difference of more than 30%, while the influence of the support time was smaller. The Sharing ratios of secondary lining in Class III surrounding rock do not exceed 12%, while those of Class V surrounding rock exceed 40%. The overall difference between the results of model tests and numerical simulations is small, which verifies the feasibility of similar material development in this study.

• 방사선산업학회지
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• 제18권3호
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• pp.195-207
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• 2024

International organizations such as IAEA and EC recommend graded approach by identifying NORM industries requiring radiation protection. In Korea, single regulation rather than graded regulation for NORM industry is applied. Therefore, it consumes more manpower and costs than necessary for both regulators and workers, and is not optimized. The purpose of this study is to analyze domestic and foreign NORM industry regulatory standards and radiological characteristics for graded approach of NORM industry in Korea. Safety reports and publications such as SRS 49 and ICRP 142 published by international organizations were investigated, and domestic and foreign NORM regulatory guidelines and legislation such as Health Canada and the Act on Protective Action Guidelines Against Radiation in the Natural Environment were investigated to indicate NORM industries and regulatory standards. The radioactivity concentration of raw materials or by-products, radiation dose by industrial process of the NORM industry identified in IAEA and Korea were investigated. Nine NORM industries in Korea were identified based on the NORM industry from IAEA and KINS survey report. Foreign countries such as Canada, UK and Denmark were executing graded approach such as classification of dose level or licensing, registration, notification based on safety assessment. Radioactivity concentration of domestic and foreign NORM industries were widespread up to 200 Bq g^-1 or higher based on industrial process and work type, and numerous NORM industries that exceeded radiation dose of 1 mSv y^-1 were indicated. Therefore, it is necessary to consider handling materials and work types of identified NORM industry when establishing graded approach for NORM industry in Korea considering domestic situation. The results of this study are expected to be used as basic data for developing methodology of graded approach for NORM industry in Korea.

• 핵의학기술
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• 제14권1호
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• pp.111-114
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• 2010

양전자 방출 단층촬영은 세포의 생화학적 변화에 따른 방사성의약품의 집적 정도를 영상화함으로서 암을 조기에 진단할 수 있는 검사방법으로 알려져 있다. 이러한 집적 정도는 여러 가지 원인에 따라 발생될 수 있는 것으로 $^{18}F$-FDG 주사량, 종양의 크기, 혈중 포도당 농도 등이 있다. 본 연구에서는 집적방사능과 2D와 3D 영상 획득이 방사능 농도(kBq/mL)에 미치는 영향에 대하여 평가하고자 한다. GE Discovery STe 16 PET/CT에서 1994 NEMA PET phantom을 이용하였으며, 배후방사능과 열소의 방사능 농도비가 1:2, 1:4, 1:8, 1:10, 1:20, 1:30 표준이 되도록 하여 2D와 3D로 영상을 획득하였다. 재구성 방법으로 2D와 3D 모두에서 반복연산법으로 반복횟수 2회, 부분집합 20을 적용하였다. 그리고 CT 감쇠보정법과 획득 시간은 10분으로 설정하였다. 또한 영상분석은 열소의 중심과 배후방사능에 동일한 관심영역을 설정 한 후 각 부분의 방사능 농도를 측정하여 비교 분석하였다. 설정된 관심영역의 배후방사능과 열소의 방사능 농도 비는 2D에서 1:1.93, 1:3.86, 1:7.79, 1:8.04, 1:18.72, 1:26.90, 3D는 1:1.95, 1:3.71, 1:7.10, 1:7.49, 1:15.10, 1:23.24 값을 얻었다. 또한 표준 방사능 농도비를 기준으로 한 백분율 차이(% Difference)는 2D에서 3.50%, 3.47%, 8.12%, 8.02%, 10.58%, 11.06%로 최소 3.47%에서 최대 11.06% 차이가 있고 3D는 3.66%, 4.80%, 8.38%, 23.92%, 23.86%, 22.69%로 최소 3.66%에서 최대 23.92%까지의 차이를 나타냈다. 방사능 농도가 증가할수록 실제 집적된 방사능 농도의 차이가 커짐을 알 수 있으며, 2D가 3D보다 평균 약 10.6% 높게 집적되어 방사능 농도 변화에 영향을 적게 받는 것으로 나타났다. 따라서 임상환자의 추적 검사에서 영상 획득 방법을 변화할 시 정확한 정량 평가를 위해서 이점을 고려하여 적용하여야 한다.

• 자원환경지질
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• 제45권3호
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• pp.277-294
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• 2012

부산의 지역의 암석 종류에 따른 토양 내 라돈 농도의 시 공간적 변화 특성과 변화 요인에 대하여 연구하였다. 토양 내 라돈($^{222}Rn$)농도와 암석 및 토양의 모원소($^{226}Ra$,$^{228}Ra$ U, Th)의 농도를 부산지역 24개 지점에서 측정하였다. 모암과 토양 내 이들 모원소들의 분포와 거동 특징을 분석하고 라돈과의 상관성을 상세히 규명하였으며, 지형에 대한 영향도 평가하였다. 토양 내 라돈 농도 측정에는 두 가지 in-situ 방법(soil probe 방법과 지중매설튜브 방법)을 적용하여 측정의 정확성에 대하여 비교하였다. 토양 내 라돈의 공간적 분포는 모암의 암석 종류에 따른 U의 농도를 전반적으로 반영하여, 화산암에 비해 심성암에 높고, 산성암>중성암>염기성암 순으로 높은 변화양상을 보였다. 그러나 동일한 모암에서 유래된 토양내의 라돈 농도에서 큰 폭의 변화가 나타나며, 이는 라돈의 모원소인 U와 $^{226}Ra$의 암석과 토양에서의 현저한 방사능 비평형 결과이다. 따라서 토양 내 라돈 농도는 이들 모원소의 암석과 토양 내 농도와의 상관성은 매우 낮게 나타나며, 암석 내 농도에 비해 토양 내 농도와 더 높은 상관성을 보였다. Th과 $^{228}Ra$은 풍화작용과 토양 발달 특성에 따라 U와 지구화학적 거동 및 부하 특징을 달리하기 때문에, 동일한 모암에서 유래된 토양에서도 토양 특징에 따라 U와 현저히 다른 복잡한 농도 변화 양상을 나타내었다. 지형구배를 이루는 경사지의 동일 심도의 토양 내 라돈농도는 위치에 따라 차이를 나타내며, 모암을 같이하는 잔류토양(부산대 내 19개 지점)내에서는 소규모 지형 변화에 의해 토양 내 라돈 농도가 6.8~29.8Bq/L 범위로 변화하였다. 토양 내 라돈 농도는 토양 특성에 따라, 정반대의 계절적 변화 양상을 보인다. 지중매설튜브 방법이 soil probe 방법에 비해 더욱 정확히 토양 내 라돈농도를 측정할 수 있어, 토양 내 라돈의 시 공간적 변화 특성에 대한 분석에 매우 유용한 것으로 나타났다.