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      • KCI등재
      • A Study on the Evaluation of Dose Equivalent and Performance Testing for the Gamma-ray and Hard X-ray Film Badges

        Kim, Soong Pyung,Chung, Woon Kwan CHOSUN UNIVERSITY 1997 Basic Science and Engineering Vol.1 No.2

        The purpose of this paper is to establish the critena for acceptable performance of and testing conditions for film-badge personnel dosimetry services. This work applies to personnel dosimetry services used for determining whole body dose equivalent for occupational exposure and absorbed dose. Asd a result, the performance index in each category, sum of the absolute value of the bias and the standard deviation value of the performance quotient, was estimated by the use of film badge algorithm and processed dose equivalents according to the standard method. Th performance in a given category was assessed as acceptable, for the deep and shallow dose equivalents, the performance index was less than 0.5. The test results is satisfied film-badghe dosimetry performance testing. These methods show a good agreement between irradiated and calculated dose within tolerance level represented in ANSi N13.11 and can e used for the dose evaluation of photons, electrons and mixtures of these radiations.

      • KCI등재

        A Study on the Oceanic Diffusion of Liquid Radioactive Effluents based on the Statistical Method

        Kim,Soong-Pyung,Lee,Goung-Jin 대한방사선 방어학회 1998 방사선방어학회지 Vol.23 No.1

        영광 원전 지역에 적용될수 있는 액체 방사성 물질의 확산 모델을 개발하였다. 영광에서의 해양 확산조건은 매우 복잡하기 때문에 수치적 모델을 적용하는 것은 매우 어렵다. 따라서 비교적 단순하면서도 신뢰성 있는 미규제 지침 1.113에서 제시한 통계적 모델을 적용하였다. 이를 통해, 발전소 운전조건이나, 피폭경로에 따른 희석 인자를 계산할 수 있는 컴퓨터 코드를 개발하였다. 액체 방사성 물질의 확산에 대해서, 혼합 범위를 따라 근거리 혼합 모델과 원거리 혼합 모델로 구분하여 모델을 개발하였다. 근거리 혼합 현상은 부력과 초기 운동량 및 난류에 의해 결정된다. 원거리 혼합에서는 대기 중의 구름확산과 유사하게 가우시안푸륨 모델을 적용할 수 있다. 서로 다른 피폭 경로에 대해 물리적 타당한 적분을 수행함으로서, 경로에 따른 희석인자를 구할 수 있었다. 개발된 모델을 사용하여 계산한 결과에 의하면, 현생 영광 ODCM에 사용되는 희석인자는 상당히 과평가되어 있음을 알 수 있다. A diffusion model of radioactive liquid effluents is developed and applied for YGN NPP's site, based on the Gaussian plume type model. Due to the complexity of oceanic diffusion characteristics of YGN site, a simple and reliable statistical model based on Reg. Guide 1.113 is developed. Also, a computer code package to calculate dilution factors as a function of plant operation conditions and pathway of radioactive materials. A liquid effluents diffusion model is developed by dividing the diffusion range into two categories, i.e., a near field mixing region and a far field maxing region. In the near field, the initial mixing is affected by a buoyance force, a high initial turbulence and momentum which is characterized by a plant operation condition and environmental conditions. The far field mixing is similar to gaseous effluents diffusion. So, beyond the near field region, welknown Gaussian plume model was adopted. A different area averages of Gaussian plume equation was taken for each radioactive exposure pathway. As a result, we can get different dilution factors for different pathways. Results shows that present dilution factors used for YGN ODCM is too much overestimated compared with dilution factors calculated with the developed model.

      • Nuclear Facilities and Public Acceptance

        Kim, Soong Pyung CHOSUN UNIVERSITY 1997 Basic Science and Engineering Vol.1 No.2

        The anti-nuclear movement related with nuclear power plant and radwaste disposal facility has been spread out widely in nuclear facility near area since the second half of 1980's. The direction of nuclear P.A. should be toward socio-cultural view for local resident's safety recognition and financial aids. Nuclear publicity may be a s preading work to transfer the public's common sence for the nuclear sagery from technological view to socio-cultural view. WHen financial is paid to local residents for accepting the nuclear related facility, the support must be decided according to reasonable criterion.

      • KCI등재

        An Improvement on the Analysis Techniques of Environmental Radioactivity Around Nuclear Power Plants

        Kim,Soong-Pyung,Chae,Gyung-Sun,Chung,Won-Kwan 대한방사선 방어학회 1995 방사선방어학회지 Vol.20 No.1

        환경방사능 분석기술은 원자력시설의 가동중 정상 및 비정상 상태시 이상판단과 지역특성에 따른 주변환경 방사능의 특성 및 거동파악 등을 하는데 필요한 기술로 원전 가동전,후 환경 방사능량을 비교함으로서 방사능 오염 및 변화상황을 파악할 수 있다. 국내에는 현재 관련법에 따라 규제기관 및 관련기관에 의한 환경감시가 계속되어오고 있으나 분석기술에 대한 한국규격이 신뢰성이 떨어지고 있다. 따라서 토양시료에 대한 감마핵종 분석에 한정하여 기수행된 측정방법 및 결과 등을 비교분석하므로서 원전주변 환경방사능 감시목적에 적합한 분석기술의 신뢰도 향상 및 상대오차율 최소화 방안을 도출하였다. An estimate of a change in radioactivity's circumstances around the nuclear power plant is validated with the results of the radioactivity measurements are compared. In this study, to further enhance the reliability of the results obtained form the environmental radioactivity measurements and analysis around the nuclear power plants that have been carried out up to the present. In the korea standard, there is the technical analysis guide for general stable chemical element's, but there is not the technical analysis guide for the radio-nuclei, therefore the environmental sample collection, the pretreatment of the sample and radionuclide analysis in the sample, the result's of the environmental radioactivity measurements by each organization, etc. are different. It is not sufficient for the database to forecasting a change in radioactivity's circumstances. A comparative study of collection and pretreatment techniques for the soil sample, the results by comparison, the method of minimizing the relative error are proposed. At one side of sample collection, there are going to considered that the surroundings of sample collection like the lay of the land, the provision of the selection standard for the area and pathway of radionuclide adhesion, the coherence of sample collection, etc.. at another side of pretreatment of the sample and measurement in the case of soil sample, how to do homogeneously the soil particle size and the standard tools, i.e. kinds of meshes, must to be selected.

      • Precipitants and Complexing Agents for Uranium

        Kim, Soong-Pyung,Hong, Wan-Hae 조선대학교 생산기술연구소 1987 生産技術硏究 Vol.9 No.1

        This project is concerned with the problem of recovering' uranium in concentrated form from dilute aqueous solutions. It has been shown that his-benzene phosphinic acid is remarkably effective in precipitation uranyl ions from dilute solutions.. Ferrous and aluminum ions did not interfere with the precipitation at the higher pH levels. but ferric ions had a deleterious effect. The use of sulphonic acid type ion-exchange resins such as Amberlite IR-120 and Dowex 50, have hear ly quantitative temoval of uranyl ion from dilute sulphuric acid solutions. Amber lite IRA-400 also gave promising results in removing uranium from phosphate solutions.

      • Adsorption of Uranyl Salts from Acidic Solutions by Activated Charcoal

        Kim, Soong-Pyung,Choe, Seung-Pyung,Park, Ki-Ju 조선대학교 생산기술연구소 1987 生産技術硏究 Vol.9 No.1

        This work indicates the removal of uranium from strongly acidic solutions by adsorption on activated charcoal. The adsorption of uranium from chloride, nitrate, perchlorate, and sulphate solutions at pH 2 can be represented by ◁화학식 삽입▷ (원문을 참조하세요) At pH's less than 2.5, the adsorption of uranium on charcoal was a function of the hydrogen ion concentration as expressed by the equation. ◁화학식 삽입 (원문을 참조하세요) The zero temperature coefficient and the reversibility of the uranium adsorption on charcoal s ugges ted a physical adsorption.

      • 제올라이트를 이용 핵폐기물의 흡착에 관한 연구

        김숭평,장우양,최승평,박복남 조선대학교 원자력연구소 1990 原子力硏究 Vol.4 No.-

        Synthetic zeolite A was prepared by reaction domestic Hadong Kaolin with sodium hydroxide solution and the sorption behavior of some typical fission products such as Sr, Ba, Ca on zeolite A were studied. It was observed that ion exchange capacities for cry stalline zeolite A were very effective. The selectivity series obtained from ion exchange standard Gibbs free energies were found to be Sr >Ba>Ca

      • 고속증식로용 Sodium pumP의 설계, 제작에 관한 연구

        김평승,장우양,박복남,최숭평 조선대학교 동력자원연구소 1988 動力資源硏究所誌 Vol.10 No.2

        The good electrical conductivity of liquid metals, and particularly that of sodium, gives the possibility of pumping or flow control by electromagnetic means. The magnetic frame can be removed or mounted at the free end of the pump pipe without interfering in the closed pipe system. Due to the eddy current losses in the annular gap, the pump can be started up without external trace heating. The discharge flows can be continuously controlled via variable -ratio transformers of thyristor regulating units.

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