• Journal of Radiation Protection and Research
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• v.18 no.1
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• pp.9-24
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• 1993

The time-dependent radioecological model applicable to Korean environment has been developed in order to assess the radiological consequences following the short-term deposition of radionuclides in an accident of nuclear power plant. Time-dependent radioactivity concentrations in foodstuffs can be estimated by the model called 'KORFOOD' as well as time-dependent and time-integrated ingestion doses. Three kinds of critical radionuclides and thirteen kinds of foodstuffs were considered in this model. Dynamic variation of radioactivities were simulated by considering several effects such as deposition, weathering and washout, resuspension, root uptake, translocation, leaching, senescence, intake and excretion of soil by animals, intake and excretion of feedstuffs by animals, etc. The input data to the KORFOOD are the time of the year when the deposition occurs, the kinds of radionuclides and foodstuffs for estimation. The time-dependent specific activities in rice and the ingestion doses due to the consumption of all considered foodstuffs were calculated with deposition time using agricultural data-base in Kori region. In order to validate results of KORFOOD, the calculated results were compared with those by a leading German model, ECOSYS-87. The comparison of results shows good agreements within a factor of ten.

• Korean Journal of Environmental Agriculture
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• v.5 no.2
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• pp.85-94
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• 1986

To study fate of carbofuran in paddy system, C-14 labelled carbofuran was applied to paddy water containing rice seedlings and time course study was made on the distribution, metabolism and chemical transformation of the systemic insecticide. Carbofuran was readily absorbed by plant root and translocated to shoots where most of the radioactivities were confined to leaf tips. The fact that gradual increases in radioactivities of both aqueous phase extracts and non-extractable fractions of plants (shoots and root) increased with incubation is taken as an evidence that reactions (phase I and II) proceed in rice plants. Carbofuran and its five metabolites were all detected by TLC in organic phase extracts of paddy plants or soil. Evidence was put forward that carbofuran and its five metabolites were all identified as aglycones of conjugates. 7-benzofuranol and 3-hydroxycarbofuran were the most abundant aglycones. Soil microbes appears to have little effects on the metabolism of carbofuran. They increased radioactivity of non-extractable fraction and reduced that of organic phase extracts of paddy soil.

• The Journal of the Petrological Society of Korea
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• v.17 no.3
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• pp.179-190
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• 2008

The distribution characteristics of some major environmental radionuclides ($^{40}K$, $^{228}Ac$, $^{226}Ra$, $^{222}Rn$) and U in rocks, soils and soil gas were studied at Geumjeong-Gu, Busan, Korea. The activities of radionuclides in granitic rocks are decreased in the odor of $^{40}K$>thorium decay series>uranium decay series. This reveals that Th was relatively more enriched in granitic rocks than U. The U content and activity of $^{226}Ra$ and $^{228}Ac$, however, don't reflect the fractionation sequence of granitic rocks in the study area. The activities of all these radionuclides and U content in soils are generally higher than in rocks, and their distribution in rocks, soils and soil gas show very low co-relationship. These facts indicate that the activities of radionuclides in soil and soil gas were greatly affected by leaching and adsorption properties of the radionuclides and their parents during weathering and pedogenetic process rather than their concentrations in parent rocks.

• Journal of Radiation Protection and Research
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• v.35 no.3
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• pp.105-110
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• 2010

Using N-type HPGe gamma spectrometer, uranium analysis technique of soil sample is developed where the chemical preprocessing is not a necessity. The results of uranium activities using the method presented in this paper were compared with those results with conventional alpha spectrometer and two results were similar from within uncertainty range. Therefore, this new method will be applied in uranium activity analysis of soil sample.

• Journal of Soil and Groundwater Environment
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• v.14 no.2
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• pp.10-16
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• 2009

Characteristics of natural radioactivity were investigated for soils collected from seven sites of different bed rocks distributed in the Keum River area of Korea by the use of a Gamma-ray spectrometry. Specific activity (SA) and SA ratio (SAR) of typical naturally occurring radioactive nuclide such as $^{226}$Ra, $^{228}$Ac and $^{40}$K were determined for the soil samples. The SA values of $^{226}$Ra, $^{228}$Ac and $^{40}$K in 41 soils of 7 sites are 26.7-485 (74.2 ${\pm}$ 72.2), 30.9-157 (90.7 ${\pm}$ 32.7) and 203-1558 (990 ${\pm}$ 203) Bq/kg, respectively. The SA of $^{226}$Ra has very different values by the soils and the sites. Especially the SA of $^{226}$Ra in a soil sample of Ogcheon site is 485 Bq/kg while most SA of 41 soil samples are < 100 Bq/kg. SA of $^{228}$Ac has a little different values with the soils and sites, however the SA of $^{40}$K has almost constant values in all soil samples. The SAR values of $^{26}$Ra/$^{228}$Ac, $^{226}$Ra/$^{40}$K and $^{228}$Ac/$^{40}$K in 41 soils of 7 sites are 0.343-6.11 (0.865 ${\pm}$ 0.883), 0.0258-0.759 (0.0814 ${\pm}$ 0.1l17) and 0.0373-0.178 (0.0945 ${\pm}$ 0.0373), respectively. The SARs of $^{226}$Ra/$^{228}$Ac and $^{226}$Ra/$^{40}$K have very different values by the soils and the sites, however the SAR of $^{228}$Ac/$^{40}$K has a little difference by the soil and sites.

• Journal of Radiation Protection and Research
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• v.22 no.1
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• pp.35-46
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• 1997

A simple and precise method of $^{14}C$ was developed to analyze $^{14}C$ in the environment samples using a commercially available $^{14}CO_2$ absorbent and a liquid scintillation counter. An air sampler and a combustion system were developed to collect HTO and $^{14}CO_2$ in the air and the biological samples simultaneously. The collection yield of $^{14}CO_2$ by the air sampler was in the range of 73-89% . The yield of the combustion system was 97%. In preparing samples for counting, the optimum ratio of $CO_2$ absorbent to the scintillator for mixing was 1:1. No variation of the specific activity of $^{14}C$ in the counting sample was observed up to 70 days after preparation of the samples. The detection limit for$^{14}C$ was 0.025 Bq/gC, which is the level applicable to the natural level of $^{14}C$. The analytical result of $^{14}C$ obtained by the present method were within ${\pm}6%$ of the relative error from the one by the benzene synthesis. The specific activity of $^{14}C$ in the air collected at Taejon during the period of October 1996 ranged from 0.26 to 0.27 Bq/gC. The specific activity of $^{14}C$ in the air collected at 1km from the Wolsong nuclear power plant a 679 MWe PHWR, was $0.54{\pm}0.03$ Bq/gC. The ranges of specific activities of $^{14}C$ in the pine needles and the vegetations from the areas around the Wolsong nuclear power plant were 0.56-0.67 Bq/gC and 0.23-1.41 Bq/gC, respectively.

• Journal of Ginseng Research
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• v.10 no.1
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• pp.108-113
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• 1986

Ginseng saponin absorbed in rat blood and liver were analyzed by High Performance Liquid Chromatography. The amount of saponin was estimated from peak area of the corresponding fraction and the specific radioactivity was then calculated, The radioactivity of the methanol-water extract of blood serum and livers of ginseng saponin administered rats decreased rapidly during the first four hours after the saponin administration. However, the radioactivity disappearance rate was relatively slow when the radioactivity was below a certain level. It seemed that the glycosides of panax ginseng were absorbed partly in the undissociated form and the saponin level of the liver might be maintained at 10-6% - 10-5% for a considerable period of time in ginseng administered rats.

• Journal of the Korean Society of Radiology
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• v.14 no.5
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• pp.643-650
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• 2020

The materials with a high processiblity for radiation shielding, in particular for 3D printable materials, are highly demanding for producing robots working in nuclear plants and designing customized personal protection equipment. In this study, we suspend tungsten particles in a polymeric matrix of either PLA or ABS to compose tungsten-polymer composite filaments; PLA and ABS are widely used for conventional FDM-based 3D printing. The weight fraction of tungsten particles can be increased up to 50% without forming macroscopic aggregates. The composite filaments can be used to print 3D architectures with any shape and geometry. To demonstrate one of potential applications, we print parts for robot actuator and assemble them to protect PCB against gamma ray.

• Journal of Nutrition and Health
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• v.12 no.3
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• pp.1-8
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• 1979

단백질을 함유하지 않은 식이를 5일간 먹인 쥐에게 동량으로 혼합된 필수 아미노산 혼합물(amino acid mixture)을 투여 하여 ornithine $\delta$-transamiaase(OT)를 유도(induction)한 군과 또한 amino acid mixture를 먹인 후 $6{\sim}9 \;1/2$시간 후에 glucose를 동시에 먹인 군에서 OT의 유도 기전을 보기 위하여 방사성 동위원소인 L-methionine-$CH_{3}-C^{14}$ 또는 L-Phenylalanine-$H^{3}$(uniformly labelled) 을 사용하여 유도전 OT를 pulse label하여 준비된 항체로 각각 유리 분리시켜서 방사능을 측정하였다. Amino acid mixture만을 투여한 군에서는zero time에 비해 OT활성은 6시간 후에 1.5배, 12시간 후에는 약 3배, 18시간 후에는 13배가 증가되었다. 또한 OT에 incorporate된 표지 아미노산의 방사능은 6시간 후에 1.5배, 12시간 후에 약 3배가 증가 되었을을 보였다. 그러나 이 기간동안 간장의 total soluble protein에 incorporate된 표지 아미노산의 방사능은 거의 증가하지 않았다. 그러므로, amino acid mixture에 의한 OT의 증가는 고유하게 유도되었으며 이때의 관성의 증가는 OT 단백질의 분해률의 감소에 의한 것이 아니라 순수하게 OT 단백질의 생합성에 의찬 증거라고 볼 수 있다. amino acid mixture를 투여한지 6시간 후에 glucose 용액을 동시에 먹인 쥐에서는 OT 활성은 증가를 하였으나 amino acid mixture만을 먹인 군보다는 약간 감소를 보였다. 또한 glucosedp이 투여된 후에는 OT에 표지 아미노산이 더 이상 incorporate되지는 않아 방사능의 증가는 보이지 않았으나 glucose가 투석될 당시보다 더 이상 감소되지는 않았다. 그러므로 glucose에 의한 유도에 대한 억제 (repression)는 단백질의 분해률의 증가에서 온 것이라기 보다는 OT 단백질의 생합성을 억제하여서 $OT_{1}$활성을 감소하지 않았는가 본다.

• Nuclear Engineering and Technology
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• v.16 no.3
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• pp.169-179
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• 1984

An efficient procedure of evaluating the fuel cladding failures occurring in the normal operations of typical PWR's has been investigated through the analysis of fission product(FP) activities in the reactor coolant using an analytical model, FIPREL code. Performed by this code is an extensive study on the sensivities of FP activities to such physical parameters as enrichment, turnup, and operation temperature of failed fuel rod as well as the effective failure size quantified in terms of the magnitude of gap release coefficient. The results of study are generally in agreement with those by PROFIP method. In the presence of tramp uranium the portion of activities released from failed rod is separated by an iterative calculation based on the activity ratios of fission nuclides chemically more stable than iodines. Obtained are the linear power density and the number of failed rods, the effective failure size, and the mass of tramp uranium. The operation experiences of 4 cycles of Kori Unit 1 are analyzed and the results show that the model is highly reliable for the survey and evaluation of fuel rod conditions during reactor operations.