• Journal of Radiation Protection and Research
• /
• 제39권4호
• /
• pp.206-212
• /
• 2014

진폐요양기관에 대한 실태조사를 실시하여 진폐요양환자에게 사용되는 흉부 CT촬영 선량이 국내외 진단 참고 준위 내에서 사용되는지 알아보았다. 진폐요양기관은 27개 중에서 운용자 콘솔 컴퓨터에서 환자 피폭선량(dose length product, $mGy^*cm$, 이하 DLP) 확인이 가능한 2-Detector 이상 설치된 17개 기관을 대상으로 하였다. 연구대상기관을 직접 연구자가 방문하여 위치잡이촬영, 조영제 사용전,후촬영 및 총 DLP 값을 각각 확인하였다. 또한, 장치의 기본 항목, 위치잡이촬영 조건, 본촬영(scanning) 조건 및 영상 획득 조건을 확인하였다. 흉부 CT촬영에서 확인된 총 DLP 값, 조영제주입전촬영 DLP 값의 상향서열 3/4 순위에 해당하는 DLP 값을 구하였다. SPSS ver. 19.0을 사용하여 전체 영상과 폐야영상 간에 조영제주입전촬영 DLP 값의 비교는 비모수 검정(Wilcoxon signed rank test)을 실시하였다. 전체영상보다 폐야영상을 얻을 때 20.2%의 유의한 DLP 값 감소를 보였다(707.2 vs. 555.9, p<0.001). 흉부 CT촬영에서 확인된 총 DLP 값의 상향서열 3/4 순위(third quartile)의 DLP 값은 $1036.1mGy{\cdot}cm$였다. 흉부 CT촬영의 조영제 주입전촬영에서 확인된 DLP 값의 상향서열 3/4 순위의 DLP 값은 $504.1mGy{\cdot}cm$였다. 진폐요양환자의 흉부 CT촬영에 사용하는 선량은 국내외 진단 참고 준위와 큰 차이를 보이지 않았다.

• 한국의류학회지
• /
• 제23권7호
• /
• pp.980-986
• /
• 1999

This study was done to ivestigate the fabrics thatminimized harmfulness of UVB(ultraviolet B) and that might product Vit. {{{{ {D }`_{3 } ^{ } }} by UVB. Twelve female subjects wearing in three different types i.e fabric A(UVB 100% protection) fabric B(UVB 50% protection) and bikinii were exposed to outdoor environment (Air Temp : 25℃, 42% R,H Air velocity : 0.13m/s UV does :6KJ/m2) Blood samples were taken 24 hours before the after the experiment in order to examine concentration of vit.{{{{ {D }`_{3 } ^{ } }} in the blood. During the experiment axillary temperature skin temperature of 7 areas(forehead Chest Upper arm, Hand Thigh Lower leg, Foot) were measured. The more irradiated areas by UVB were the more the concentration of serum 25(OH){{{{ {D }`_{3 } ^{ } }} were significantly. Mean skin temperature was significantly low levekl in wearing the fabric of UVB 50% protection (p<0.001) Axillary temperature was significantly high level in wearing the fabric of UVB 50% protection (p<0.001). Therefore the fabric of UVB 50% protection intercepts the radiation and has advantage to give off body heat over other fabrics

• Journal of Radiation Protection and Research
• /
• 제10권1호
• /
• pp.3-13
• /
• 1985

주요 핵분열 생성물인 세슘-137, 장수명 핵종과 세륨-144, 희토류원소 그리고 부식 생성물인 코발트-60등의 제올라이트 A, 제올라이트 F-9(Faujasite) 그리고 비정형 제올라이트에 대한 흡착거동을 염농도 0.01 M부터 2.0 M 질산과 질산암모늄 그리고 교반시간 15분부터 90분까지 15분 간격으로 검토하였다. Kd 값은 Batch 실험방법으로 구했다. 결론으로 주요핵종의 분리 제거의 최적조건은 비정질 제올라이트, 0.01 M-질산과 0.1 M-질산암모늄, pH 4, 교반시간 한시간 그리고 가장 효율높은 핵종은 세슘 -137이다.

• Journal of Radiation Protection and Research
• /
• 제41권4호
• /
• pp.350-353
• /
• 2016

Background: Various characteristics such as size distribution, chemical component and radio-activity have been analyzed for radioactive aerosols released from Fukushima Daiichi Nuclear Power Plant. Measured results for radioactive aerosols suggest that the potential transport medium for radioactive cesium was non-sea-salt sulfate. This result indicates that cesium isotopes would preferentially attach with sulfate compounds. In the present work the attachment behavior of fission products to aqueous solution aerosols of sodium salts has been studied using a generation system of solution aerosols and spontaneous fission source of $^{248}Cm$. Materials and Methods: Attachment ratios of fission products to the solution aerosols were compared among the aerosols generated by different solutions of sodium salt. Results and Discussion: A significant difference according as a solute of solution aerosols was found in the attachment behavior. Conclusion: The present results suggest the existence of chemical effects in the attachment behavior of fission products to solution aerosols.

• 한국콘텐츠학회논문지
• /
• 제9권7호
• /
• pp.211-217
• /
• 2009

본 연구에서는 알긴산올리고당의 일부 방사선 방어효과를 규명하기 위해 마우스에 3 Gy 선량의 방사선을 1회 전신 조사하여 방사선 유도 nitric oxide를 측정하였다. 측정결과 방사선조사 대조군에서 nitric oxide 생성이 하강된 반면 방사선조사 전 3일간 처치군 및 방사선조사 후 3일간 처치군에서 유의한 생성 증가를 보였고, 특히 방사선조사 전 3일간 처치군에서 가장 큰 차이를 보였다(P<0.001). 결론적으로, 항산화효과가 탁월한 알긴산올라고당은 nitric oxide의 생성 증가를 촉진시킴으로써 일부 방사선 방어작용을 수행한다는 사실을 규명하였고, 화학적 독성이 적은 자연산생물이 방사선방어제로 활용될 수 있음을 확인하였다.

• 대한기계학회논문집B
• /
• 제26권11호
• /
• pp.1503-1512
• /
• 2002

From the view of the environmental protection against the use of fossil fuels, a great of efforts have been exerted to find an alternative energy source. Hydrogen may become an alternative However the product species of the hydrogen flame is only $H_2O$, which emits only non-luminous radiation so the radiation from it is much smaller than that for a hydrocarbon flame. In this study, the authors designed and fabricated a laboratory scale test furnace to study thermal characteristics of hydrogen-air diffusion flame. In addition. the effects of addition of reacting as welt as non-reacting solid particles were experimentally investigated. Among the total heat flux to the wall, about 75 % was occupied by radiation while 25% by convection. When the aluminum oxide (Al$_2$O$_3$) particles were added, the radiative heat flux was reduced due to heat blockage effects. On the other hand, the total as well as the radiative heat flux was increased when the carbon particles were seeded, since the overall temperature increased. The effects of swirl and excess air ratio were also examined.

• Nuclear Engineering and Technology
• /
• 제36권6호
• /
• pp.549-558
• /
• 2004

TTo comply with increasingly strict regulations for protection against radiation exposure, many nuclear power plants have been working ceaselessly to reduce and control both the radiation sources within power plants and the radiation exposure experienced by operational and maintenance personnel. Many research studies have shown that deposits of irradiated corrosion products on the surfaces of coolant systems are the main cause of occupational radiation exposure in nuclear power plant. These corrosion product deposits on the fuel-clad surface are also known to be main factors in the onset of axial offset anomaly (AOA). Hence, there is a great deal of ongoing research on water chermistry and corrosion processes. In this study, a magnetic filter with permanent magnets was devised to remove the corrosion products in the coolant stream by taking advantage of the magnetic properties of the corrosion products demonstrated a removal efficiency of over 90% for particles above 5${\mu}m$. This finding led to the construction of an electromagnetic device that causes the metallic particulates to flocculate into larger aggregates of about 5${\mu}m$ in diameter by using a novel application of electromagnetic flocculation on radioactive corrosion products.

• Journal of Radiation Protection and Research
• /
• 제14권2호
• /
• pp.30-36
• /
• 1989

고리 1호기의 사용후 핵연료에 함유된 핵종중 핵임계도에 미치는 영향이 큰 22개 핵종에 대한 핵단면적 자료를 XLACS-II에 의해서 ENDF/B-IV로 부터 취해서 FISSLIB(51군 핵단면적 자료)를 만들었다. 그리고 AMPX 조직에 의해서 DLC-43/CSRL 자료로 부터 생산된 51군 핵단면적 자료와 함께 사용할 수 있도록 하였다. 한편 BNL-325와 FISSLIB을 비교하여 후자의 유용성을 확인하였다. 그리고 FISSLIB에 수록된 핵분열 생성물 핵종에 대한 핵군단면적을 기본 입력자료로 하여 무한 배열된 고리 1호기 사용후 핵연료봉에 대한 핵임계도 계산을 수행하였다. 그 결과 냉각기간에 따라 핵분열 생성물 핵종을 고려할 때의 핵임계도는 그것을 무시할 때보다 9-14%의 감소효과를 나타냈다.

• Journal of Radiation Protection and Research
• /
• 제37권2호
• /
• pp.63-69
• /
• 2012

The second phase of the national program for fusion energy development in Korea starts from 2012 for design and construction of the fusion DEMO reactor. Radiological assessment for the fusion reactor is one of the key tasks to assure its licensability and the starting point of the assessment is determination of the source terms. As the first effort, the activities of the coolant due to activated corrosion product (ACP) were estimated. Data and experiences from fission reactors were used, in part, in the calculations of the ACP concentrations because of lack of operating experience for fusion reactors. The MCNPX code was used to determine neutron spectra and intensities at the coolant locations and the FISPACT code was used to estimate the ACP activities in the coolant of the fusion DEMO reactor. The calculated specific activities of the most nuclides in the fusion DEMO reactor coolant were 2-15 times lower than those in the PWR coolant, but the specific activities of $^{57}Co$ and $^{57}Ni$ were expected to be much higher than in the PWR coolant. The preliminary results of this study can be used to figure out the approximate radiological conditions and to establish a tentative set of radiological design criteria for the systems carrying coolant in the design phase of the fusion DEMO reactor.

• Journal of Radiation Protection and Research
• /
• 제39권4호
• /
• pp.176-181
• /
• 2014

The object of this paper is to evaluate the fission product inventories and radiological doses in a non-LOCA event, based on the U.S. NRC's regulatory methodologies recommended by the TID-14844 and the RG 1.195. For choosing a non-LOCA event, one fuel assembly was assumed to be melted by a channel blockage accident. The Hanul nuclear power reactor unit 6 and the CE $16{\times}16$ fuel assembly were selected as the computational models. The burnup cross section library for depletion calculations was produced using the TRITON module in the SCALE6.1 computer code system. Based on the recently licensed values for fuel enrichment and burnup, the source term calculation was performed using the ORIGEN-ARP module. The fission product inventories released into the environment were obtained with the assumptions of the TID-14844 and the RG 1.195. With two kinds of source terms, the radiological doses of public in normal environment reflecting realistic circumstances were evaluated by applying the average condition of meteorology, inhalation rate, and shielding factor. The statistical analysis was first carried out using consecutive three year-meteorological data measured at the Hanul site. The annual-averaged atmospheric dispersion factors were evaluated at the shortest representative distance of 1,000 m, where the residents are actually able to live from the reactor core, according to the methodology recommended by the RG 1.111. The Korean characteristic-inhalation rate and shielding factor of a building were considered for a series of dose calculations.