• 한국대기환경학회:학술대회논문집
• /
• 한국대기환경학회 2003년도 추계학술대회 논문집
• /
• pp.529-530
• /
• 2003

우라늄(U-238)의 붕괴과정에서 생성되는 라돈(Rn-222)은 다른 물질과 화학적으로 결합 또는 부착하지 않는 불활성 기체이고 상대적으로 긴 반감기를 갖고 있기 때문에 충분한 시간 동안 공기중에 머물러 있으므로 다른 자연방사선원에 비하여 라돈과 라돈자손에 의한 일반인의 자연방사선피폭 기여도가 가장 높다(Jamil K. 1997). 이미 세계 여러 나라에서는 라돈피폭에 기인한 건강상의 위해를 인식하여 주택을 비롯한 여러 생활공간의 실내 및 음용수 중의 라돈농도에 대한 대규모적인 측정을 수행하고 있으며, 그 결과 미국 내 상당수의 주택이 미국 환경청에서 권고치(action level)로써 권고하고 있는 150 Bq/m3(실내공기중)와 11.100 Bq/m3(음용수중)응 초과하는 것으로 나타났다(U,S,EPA, 1992).(중략)

• 대한전기학회:학술대회논문집
• /
• 대한전기학회 1987년도 정기총회 및 창립40주년기념 학술대회 학회본부
• /
• pp.234-238
• /
• 1987

In this paper, the used specimen composition was added basic additives ($Bi_2O_3\;lmol%$, $Sb_2O_3\;lmol%$, CoO 0.5 mol%, MnO 0.5mol%) to ZnO powder, and $TiO_2$ (1,2,3,4 mol%) to the above basic composition. It appears that there are four regions of conduction current depended upon the strength of the applied electric field ; Ohimic region, Poole-Frenkel region, Schottky region and Tunneling region. Increasing of $TiO_2mol%$, the breakdown voltages of ZnO ceramic varistors are decreased. The decrease of breakdown voltages was explained with the decrease of potential barrier height. Moreover, V-I characteristics with temperature dependence are decreased with increasing of $TiO_2mol%$.

• Nuclear Engineering and Technology
• /
• 제33권2호
• /
• pp.156-165
• /
• 2001

A radiological safety assessment was performed for a hypothetical near-surface radioactive waste repository as a simple screening calculation to identify important nuclides and to provide insights on the data needs for a successful demonstration of compliance. Individual effective doses were calculated for a conservative ground water pathway scenario considering well drilling near the site boundary. Sensitivity of resulting ingestion dose to input parameter values was also analyzed using Monte Carlo sampling. Considering peak dose rate and assessment time scale, C-14 and T-129 were identified as important nuclides and U-235 and U-238 as potentially important nuclides. For C-14, the dose was most sensitive to Darcy velocity in aquifer The distribution coefficient showed high degree of sensitivity for I-129 release.

• Structural Engineering and Mechanics
• /
• 제17권6호
• /
• pp.879-898
• /
• 2004

A method of making simply supported girders continuous is described for bridges with spans of 30-45 m. The splicing method takes advantage of an induced secondary moment to transform the self-weight stresses in the precast simply supported girders into values representative of a continuous girder. The secondary moment results from prestressing of continuity tendons and detensioning of temporary tendons in the girders. Preliminary sections are selected for spliced U-girder bridges with a range of span lengths. Use of the proposed technique results in girder depth reductions of 500-800 mm when compared to standard simply supported I-girder bridges. The flexural behavior of an example bridge with 40-m spans is examined to illustrate the necessary considerations for determining the optimum sequence of splicing operations.

• 한국방사선학회논문지
• /
• 제7권1호
• /
• pp.31-36
• /
• 2013

우라늄($^{238}U$)의 붕괴과정에서 생성되는 방사성기체인 라돈($^{222}Rn$)은 발생원 중 토양에서 85 % 이상으로 토양의 공극률이 클수록 토양 밖으로 방출할 수 있는 가능성이 많은 동위원소이다. 라돈으로부터 인체를 보호하기 위해서 적절한 대책을 세우는데 무엇보다도 정확한 측정기술의 개발이 선행되어야 한다. 이에 본 연구는 고순도게르마늄(HPGe) 검출기를 이용한 감마선 분광분석법으로 라돈을 측정할 경우에는 불안정한 자연방사능의 백그라운드 문제를 줄일 수 있고, 라듐과 라돈의 딸 핵종들을 방사평형에 이르게 한 후 라돈 농도를 측정하였으며, 토양시료에서의 감마선 방출핵종 및 에너지 스펙트럼을 분석하였다.

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2004년도 학술논문집
• /
• pp.407-417
• /
• 2004

본 연구는 우라늄변환시설의 해체과정에서 발생되는 콘크리트 및 구성부품에 대한 알파분광과 감마분광에 대한 방사선계측방법의 타당성을 입증하고자 한다. 우라늄변환시설내의 구성부품 및 내부벽면은 천연우라늄 물질로 오염되어있다. 스테인레스 스틸 파이프와 벽면의 콘크리트의 일부에 대하여 시료를 채취하고 알파분석과 감마분석을 수행하였다. 천연우라늄 시료(AUC)의 측정에서 0.01 Bq/g 이상에서는 알파선 측정결과와 감마선 측정결과가 잘 일치하지만, 0.005 Bq/g의 낮은 농도에서는 감마선 측정결과가 상대적으로 높게 평가된다. 변환공정의 천연우라늄인 $^{238}U$은 $^{214}Pb$, $^{214}Bi$ 와 $^{234}Th$, $^{234m}Pa$을 비교 측정하여 그 농도를 구할 수 있다. 우라늄변환시설의 벽면은 대부분 우라늄으로 오염되어있다. 우라늄변환시설 해체과정에서 발생되는 배경방사능 준위의 폐기물을 감마분광법을 이용하여 계측하여 보수적인 평가 자료로 활용할 수 있다.

• 한국식품영양학회지
• /
• 제11권1호
• /
• pp.6-10
• /
• 1998

탈취온도가 옥수수기름의 냉각시험 및 발연점에 미치는 영향을 측정해 보았다. 탈취온도가 상승할수록 투입되는 탈납유 대비 탈취유의 냉각시험 결과는 현저히 하락하였으며, 26$0^{\circ}C$ 이상에서는 그 정도가 극심하여 이는 포화도 증가 및 SU2, S2U, S3형 triglycerides 함량 증가와 상관관계가 있는 것으로 추측되었다. 한편, 발연점은 탈취온도 24$0^{\circ}C$에서 가장 높은 242$^{\circ}C$를 나타내었고, 탈취온도 245~27$0^{\circ}C$의 범위에서는 235~238$^{\circ}C$로 하락하였으며, 이러한 현상은 시료유의 산값과 반비례하는 것으로 나타났다. 따라서 일반 이화학적 특성, 지방산 조성 등과 함께 냉각시험 및 발연점에서도 고온탈취는 악영향을 미치는 것으로 판명되었다.

• Journal of the korean society of oceanography
• /
• 제35권1호
• /
• pp.16-33
• /
• 2000

In order to measure the vertical fluxes of particles and reactive radionuclides such as thorium and polonium isotopes, Dunbar-type sediment traps were freely deployed at the Ulleung Basin and in warm and cold water masses around the polar front of the East Sea. We estimated the ratios of the catched (F) to the predicted $^234$Th fluxes (P) using natural tracers pair $^234$Th-$^238$U. The F/P ratios are decreased with increasing water depth. Whereas the concentrations of suspended particles are homogeneous in water column, the mass fluxes are also decreased with increasing water depth like the F/P ratios. These facts indicate that organic matters of settling particles are destructed within the euphotic layer due to decomposition. Whereas regenerations of sinking particles are negligible in the cold water mass, about 80% of them are regenerated in the warm water mass during falling of large particles. These downward mass fluxes are closely correlated with their primary productions in euphotic zone. The activities of $^234$Th, $^228$Th and $^210$Po in the sinking material were increased with water depth. Because $^234$Th steadily produced in the water column are cumulatively adsorbed on the surface of sinking particles, vertical $^234$Th fluxes were observed to increase with water depth. Therefore, these sinking particles play important roles in transporting the particle reactive elements like thorium from surface to the deep sea. The scavenging processes including adsorption and settling reactions generate radio-disequilibrium between daughter and parent nuclides in water column. The activity ratios of $^234$Th/$^238$U and $^228$Th/$^228$Ra were observed to be < 1.0 in the surface water and approached to be equilibrium below the thermocline. The extent of the deficiency of daughter nuclides compared to the parents nuclide was highly correlated with the vertical particle flux. Because most of the $^210$Po in the surface water are scavenged on a labile phase and are recycled at sub-surface depths (< 200 m), the $^210$Po are always observed to be excess activities compared to $^226$Ra in surface water.

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

• Nuclear Engineering and Technology
• /
• 제46권6호
• /
• pp.837-846
• /
• 2014

A lead slowing down spectrometer (LSDS) is under development for analysis of isotopic fissile material contents in pyro-processed material, or spent fuel. Many current commercial fissile assay technologies have a limitation in accurate and direct assay of fissile content. However, LSDS is very sensitive in distinguishing fissile fission signals from each isotope. A neutron spectrum analysis was conducted in the spectrometer and the energy resolution was investigated from 0.1eV to 100keV. The spectrum was well shaped in the slowing down energy. The resolution was enough to obtain each fissile from 0.2eV to 1keV. The detector existence in the lead will disturb the source neutron spectrum. It causes a change in resolution and peak amplitude. The intense source neutron production was designed for ~E12 n's/sec to overcome spent fuel background. The detection sensitivity of U238 and Th232 fission chamber was investigated. The first and second layer detectors increase detection efficiency. Thorium also has a threshold property to detect the fast fission neutrons from fissile fission. However, the detection of Th232 is about 76% of that of U238. A linear detection model was set up over the slowing down neutron energy to obtain each fissile material content. The isotopic fissile assay using LSDS is applicable for the optimum design of spent fuel storage to maximize burnup credit and quality assurance of the recycled nuclear material for safety and economics. LSDS technology will contribute to the transparency and credibility of pyro-process using spent fuel, as internationally demanded.