• Nuclear Engineering and Technology
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• 제51권2호
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• pp.377-383
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• 2019

Targeting at simulating the application of thorium-uranium (TU) fuel in the CANDU-6 reactor, this paper analyzes the process using the code DRAGON/DONJON where the discrete TU fuel pins are applied in the CANDU-6 reactor under the time-average equilibrium refueling. The results show that the coolant void reactivity of the assembly analyzed in this paper is lower than that of 37-element bundle cell with natural uranium and 37-element bundle cell with mixed TU fuel pins; that the max time-average channel/bundle power of the core meets the limits - less than 6700kW/860 kW; that the fuel conversion ratio is higher than that of the CANDU-6 reactor with natural uranium; and that the exit burnup increases to 13400 MWd/tU. Thus, the simulation in this paper with the fuel in the 37-element bundle cell using discrete TU fuel pins can be considered to be applied in CANDU-6 reactor with adequate modifications of the core structure and operating modes.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(1)
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• pp.35-40
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• 1995

Considering the higher discharge burnup, lower channel refuelling rate, lower linear element rating(LER), lower coolant void reactivity and axial power shape, CANFLEX-RU fuel bundle is optimized for CANDU-6 by grading the fissile composition in the ring-wise of the bundle and by applying fuel management scheme appropriately. The fissile composition of the fuel bundle is graded as the recovered uranium (0.9 w/o U-235) in the outer and intermediate elements, depleted Uranium (0.2 w/o U-235) in the center element, natural uranium (0.71 w/o U-235) in the inner elements. Enrichment is not required for these fuel. The fissile composition is optimized by lattice calculation and by time-averaged reactor simulation. CANFLEX-RU optimized for CANDU-6 resulted to be the 15% lower channel refuelling rate, acceptable axial power profile and power envelope, 70% higher discharge burnup, 15% lower LER and not increase coolant void reactivity compared with the 37-element natural uranium bundle for CANDU-6.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.299-303
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• 2001

Using ultrasound techniques, the Korea Atomic Energy Research Institute has measured chest wall thicknesses of a group of male workers at the Korea Atomic Energy Research Institute. A site-specific biometric equation has been developed for these workers. Chest wall thickness is an important modifier on lung counting efficiency. These data have been put into the perspective of the ICRP recommended dose limits for occupationally exposed workers: 100 mSv in a 5-year period with a maximum of 50 mSv in anyone year. For measured chest wall thicknesses of 1.9 cm to 4.1 cm and a 30 min counting time, the achievable MDAs for natural uranium in the KAERI lung counter vary from 5.75 mg to 11.28 mg. These values are close to, or even exceed, the predicted amounts of natural uranium that will remain in the lung (absorption type M and S) after an intake equal to the Annual Limit on Intake corresponding to a committed dose of 20 mSv. This paper shows that the KAERI lung counter probably cannot detect an intake of Type S natural uranium in a worker with a chest wall thickness equal to the average value (2.7 cm) under routine counting conditions.

• 통합자연과학논문집
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• 제10권4호
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• pp.225-231
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• 2017

Cryptand resins were synthesized by mixing 1-aza-18-crown-6 macrocyclic ligand with styrene divinylbenzene copolymer having 1%, 2%, 5%, and 10% crosslink by a substitution reaction. These synthetic resins were confirmed by chlorine content, elementary analysis, SEM, surface area, and IR-spectrum. As the results of the effects of pH, crosslink of synthetic resin, and dielectric constant of a solvent on uranium ion adsorption for resin adsorbent, the uranium ion showed high adsorption at pH 3 or over. Adsorption selectivity for the resin in methanol solvent was the order of uranium ($UO_2{^{2+}}$) > calcium ($Ca^{2+}$) > neodymium ($Nd^{3+}$) ion, adsorbability of the uranium ion was the crosslink in order of 1%, 2%, 5%, and 10% and it was increased with the lower dielectric constant.

• Toxicological Research
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• 제30권2호
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• pp.117-120
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• 2014

Uranium is toxic and radioactive traces of it can be found in natural water and soils. High concentrations of it in biological systems cause genetic disorders and diseases. For the in vivo diagnosis, micro and nano range detection limits are required. Here, an electrochemical assay for trace toxic uranium was searched using stripping voltammetry. Renewable and simplified graphite pencils electrode (PE) was used in a three-electrode cell system. Seawater was used instead of an electrolyte solution. This setup can yield good results and the detection limit was attained to be at $10{\mu}gL^{-1}$. The developed skill can be applied to organic liver cell.

• Nuclear Engineering and Technology
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• 제31권5호
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• pp.445-454
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• 1999

This work describes the adaptation of extractive scintillation by URAE $X^{TM}$ with a photon-electron rejecting alpha liquid scintillation (PERAL $S^{)}$ spectrometer to the analysis of uranium in aqueous samples. The extraction efficiency of the system was evaluated under varing chemical conditions including pH, and sample-cocktail volume ratio. Isotopic information from the (PERAL $S^{)}$ spectrum of natural uranium was obtained using a curve fitting routine. Comparisons of the result with that obtained from alpha spectrometry method using ion implanted silicon detector showed good agreement.t.

• 지질공학
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• 제24권4호
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• pp.535-550
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• 2014

지하수내 존재하고 있는 자연방사성물질인 우라늄과 라돈-222의 산출특성과 지화학적 기원을 알아보기 위해 괴산지역 연구부지내 120 m 깊이의 지하수 관정을 시추하여 심도별 시추코어의 암석화학적 특성과 지하수의 화학적 특성을 분석하였다. 시추코어 샘플 분석과 함께 더블패커시스템과 베일러를 이용하여 8개의 심도별 지하수 시료를 채취하여 지화학적 특성 분석을 수행하였다. 시추코어 분석결과, 주요 암종은 화강반암과 점판암이었으며 일부 구간에서는 탄산염암과 석회규산염암, 페그마타이트가 확인되었다. 심도별 지하수의 pH는 7.8~8.4의 범위이며, 화학적 유형은 Na-$HCO_3$형태를 보였다. 암석 및 광물 내 우라늄과 토륨의 함량은 각각 < 0.2~14.8 ppm과 0.56~45.0 ppm의 범위였으며, 암석현미경과 전자현미경(EPMA) 관찰 결과 자연방사성원소(우라늄) 함유 광물은 흑운모내 포획된 모나자이트 광물인 것으로 확인되었다. 우라늄은 이들 광물의 주요 구성원소를 치환하여 존재하는 것으로 보이며 파쇄대와 같은 주요 대수층 구간에서 용해되어 지하수와 함께 용출되는 것으로 보인다. 라돈-222의 함량은 우라늄의 함량과 어떠한 상관성을 보이지 않았으며 향후, 라돈가스 기원 추적을 위해서는 헬륨과 네온 등 영족기체 동위원소비를 이용한 간접적인 방법을 적용하여 분석할 필요가 있을 것으로 판단된다.

• Nuclear Engineering and Technology
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• 제37권5호
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• pp.479-490
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• 2005

The thermalhydraulic performance of a CANDU-6 reactor loaded with various CANFLEX fuel bundles is evaluated by the NUCIRC code, which is incorporated with recent models of pressure drop and critical heat flux (CHF) predictions based on high-pressure steam-water tests for the CANFLEX bundle as well as a 37-element bundle. The distributions of channel flow rate, channel exit quality, critical channel power (CCP), and critical power ratio (CPR) for the CANFLEX bundles (with natural or recycled uranium fuel) in the CANDU-6 reactor fuel channel are calculated by the code. The effects of axial and radial heat flux on CCP are evaluated by assuming that the recycled uranium fuel (CANFLEX-RU) has the same geometric data as the natural uranium fuel bundle (CANFLEX-NU), but a different power distribution due to different fuel composition and refueling scheme. In addition, the effects of pressure tube creep and bearing-pad height are examined by comparing various results of uncrept, and $3.3\%\;and\;5.1\%$ crept channels loaded with CANFLEX bundles with 1.4 mm or 1.7 mm high bearing-pads with those of the 37-element bundle. The distributions of the channel flow rate and CCP for the CANFLEX-NU or -RU bundle show a typical trend for a CANDU-6 reactor channel, and the CPRs are maintained above at least 1.444 (NU) or 1.455 (RU) in the uncrept channel. The enhanced CHF of the CANFLEX bundle (particularly with 1.7mm height bearing-pads) produces a higher thermal margin and considerably less sensitivity to CCP reduction due to the pressure tube creep than the 37-element bundle. The CCP enhancement due to the raised bearing-pads is estimated to be about $3\%\~5\%$ for the CANFLEX-NU and $2\%\~6\%$ for the CANFLEX-RU bundle, respectively.

• 한국환경과학회지
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• 제27권8호
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• pp.651-663
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• 2018

The hydrochemistry of groundwater from 47 wells in the Chungwon area, Korea was analyzed to examine the occurrence of natural radionuclides like uranium and radon. The range of Electrical Conductivity (EC) value in the study area was $67{\sim}1,404{\mu}S/cm$. In addition to the high EC value, the content of cations and anions also tends to increase. Uranium concentrations ranged from $ND{\sim}178{\mu}g/L$ (median value, $0.8{\mu}g/L$) and radon concentrations ranged from 80~12,900 pCi/L (median value, 1,250 pCi/L). Uranium concentrations in one well, that is 2.8% of the samples, exceeded $30{\mu}g/L$, which is the Maximum Contaminant Level (MCL) proposed by the US Environmental Protection Agency (EPA), based on the chemical toxicity of uranium. Radon concentrations in three wells, that is 6% of the samples, and one well, that is 2.8% of the samples, exceeded 4,000 pCi/L (AMCL of the US EPA) and 8,100 pCi/L (Finland's guideline level), respectively. Concentrations of uranium and radon related to geology of the study area show the highest values in the groundwater of the granite area. The uranium and radon contents in the groundwater were found to be low compared to those of other countries with similar geological settings. It is likely that the measured value was lower than the actual content due to the inflow of shallow groundwater by the lack of casing and grouting.

• 지질공학
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• 제29권4호
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• pp.495-508
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• 2019

원주지역 지하수의 수리지화학 및 자연방사성물질인 우라늄과 라돈의 산출특성을 규명하기 위하여 40개 관정을 대상으로 시료를 채취하고 분석하였다. 연구지역 지하수의 EC는 최소 73에서 최대 400 μS/cm (평균 212 μS/cm)의 범위를 나타내고 있으며, EC의 증가와 더불어 주요 용존 양이온과 음이온의 함량도 증가하는 경향을 나타낸다. 우라늄 농도는 0.06~50.5 ㎍/L (중앙값 1.55 ㎍/L)로 넓은 분포를 보여주고 있으며, 라돈은 67~8,410 pCi/L (중앙값 1,915 pCi/L)의 범위를 나타내고 있다. 우라늄 농도에서 미국 EPA MCL 30 ㎍/L를 초과한 곳은 3개소로 전체 시료수의 7.5%에 해당된다. 라돈의 경우, 미국 EPA AMCL(Alternative Mximum Contaminant Level) 4,000 pCi/L를 초과한 곳은 9개소로 전체 시료수의 22.5%이다. 이중 핀란드의 음용 제안치인 8,100 pCi/L를 초과하는 시료는 1개소이다. 연구지역에서 지질별 지하수의 우라늄과 라돈 농도는 흑운모화강암 지역의 지하수에서 가장 높다. 연구지역 지하수의 우라늄과 라돈 함량은 유사한 지질을 가지는 외국에 비하면 낮은 것으로 나타났다. 이는 우리나라 지하수 관정의 특성상 케이싱 및 그라우팅이 미비한 관정이 많으므로 천부 지하수의 공내 유입을 의심할 수 있다. 이러한 관정의 특성으로 인하여 실제 함량보다 낮게 검출되었을 가능성을 배제할 수 없다.