• Journal of the Korean Society of Radiology
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• v.6 no.1
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• pp.79-82
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• 2012

Iodine is one of important nuclides to be checked for radiation exposure after nuclear power facility accidents. After Chernobyl accident, it was observed that there is a greater amount of organic iodine in the atmosphere than inorganic iodine. In this study, we not only varied the amount of sample being exposed to $^{131}I$ and the duration of exposure to $^{131}I$ but also diluted the sample in distilled water and mixed the sample in kelp and liquid $^{131}I$ to measure and analyze the radiation detection levels. We concluded that the radiation levels were not high enough to be harmful to human body. The radiation from $^{131}I$ decreased over time, and we calculated the half life at 7-9 days. We found that the radiation from any sample containing $^{131}I$ was halved by up to 7days.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.614-620
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• 2003

KAERI has developed DUPIC nuclear fuel with the refabrication of spent PWR fuel discharged from domestic nuclear power plant by a dry process at M6 hot-cell in IMEF To verify the performance of DUPIC nuclear fuel, irradiation test at the operating conditions of commercial power plant is essential. Since the HANARO research reactor of KAERI does not have fuel test loop(FTL) for irradiating nuclear fuel under high temperature and high pressure conditions, DUPIC fuel cannot be irradiated in the FTL of HANARO. In the 13-th PRM among Korea, Canada, USA and IAEA, AECL proposed that KAERI fabricated DUPIC fuel can be irradiated in the FTL of the NRU research reactor without charge of neutrons. The transportation quantity of DUPIC fuel to Canada is 10 elements(about 6kg). This transportation package is classified as the 7-th class according to "recommendation on the transport of dangerous goods" made by the United Nations. In case of air shipment, until now, there is no proper air transportation cask for DUPIC fuel. In case of sea transportation is possible but requires very high cost.high cost.

• Journal of Radiation Protection and Research
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• v.22 no.4
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• pp.251-261
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• 1997

A package to transport the high level radioactive materials is required to withstand the hypothetical accident conditions as well as normal transport conditions according to IAEA standards and domestic regulations. The regulations require that the package should maintain the shielding, thermal and structural integrities to release no radioactive material. In general, safety evaluation of packages is performed by experimental methods using scale model and/or analytical methods using computer codes. This paper presents the safety evaluation of package to transport the radioisotopes produced in the HANARO to the radioisotope production facility. Radiation shielding, thermal and structural analyses were peformed using the computer codes. It has been verified that the package is safe under hypothetical accident conditions as well as normal transport conditions.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.7 no.2
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• pp.115-124
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• 2009

Cryogenic cutting technology is one of the most suitable technologies for dismantling nuclear facilities due to the fact that a secondary waste is not generated during the cutting process. In this paper, the feasibility of cryogenic cutting technology was investigated by using a computer simulation. In the computer simulation, a hybrid method combined with the SPH (smoothed particle hydrodynamics) method and the FE (finite element) method was used. And also, a penetration depth equation, for the design of the cryogenic cutting system, was used and the design variables and operation conditions to cut a 10 mm thickness for steel were determined. Finally, the main components of the cryogenic cutting system were manufactures on the basis of the obtained design variables and operation conditions.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.9 no.1
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• pp.13-21
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• 2011

To characterize the site specific properties of a study area for high-level radioactive waste disposal research in KAERI, the several geological investigations such as surface geological surveys and borehole drillings were carried out since 1997. Especially, KURT (KAERI Underground Research Tunnel) was constructed to understand the further study of geological environments in 2006. As a result, the first geological model of a study area was constructed by using the results of geological investigation. The objective of this research is to construct a hydrogeological model around KURT area on the basis of the geological model. Hydrogeological data which were obtained from in-situ hydraulic tests in the 9 boreholes were estimated to accomplish the objective. And, the hydrogeological properties of the 4 geological elements in the geological model, which were the subsurface weathering zone, the log angle fracture zone, the fracture zones and the bedrock were suggested. The hydrogeological model suggested in this study will be used as input parameters to carry out the groundwater flow modeling as a next step of the site characterization around KURT area.

• Proceedings of the ESK Conference
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• 1996.10a
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• pp.171-178
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• 1996

CFMS(Critical Function Monitoring System)는 원자력발전소의 비상시에 운전원에게 보조장보를 제공하는 지원시스템이다. 본 연구에서는 원자력발전소 울진 3&4호기 CFMS의 화면설계에 대한 인간 공학적 검토를 수행하였다. CFMS에 대한 규제 및 법규를 만족시키는 것과 CFMS 화면설계가 운전원에게 편의성을 제공할 수 있는지에 대한 인간공학적 타당성 평가의 사례를 제시하고자 한다. 본 연구에서는 인간공학적 검토의 공식적인 체계를 설정하기 위하여, CFMS 설계에서 필요한 인간공학 업무를 규정하고 수행절차를 기술하는 인간공학 프로그램 계획 (Human Factors Engineering Program Plan; HFEPP)과 설계평가의 방법과 업무 내용을 기술하는 확인 및 검증 프로그램 계획(Human Factors Engineerign Verification and Validation Plan; HFE V&V Plan)을 개발하였다. CFMS 설계에 대한 인간공학적 확인 및 검증을 위하여 CFMS의 정보 가용성 (information availability)과 화면 적합성 (display suitability)을 확인하였다. 정보 가용성의 확인은 CFMS 설계 요건서에서 정의된 정보를 중심으로 한 필요정보의 목록과 CFMS 화면상에서 제공되는 정보의 목록을 비교함으로써 수행되었다. 화면 적합성의 확인은 검토항목 선정, 검토양식 개발, 전문가 검토, 실험검토 등의 과정을 통하여 수행되었다. 관련 규제 문건으로 부터 규제요건상 만족해야할 최소한의 검토항목을 선정하고 검토양식을 개발하였으며, 인간공학 전문가들의 주관적 평가를 통하 여 수행되었다. 또한 화면의 조작방식에 대한 상세검토를 수행하였다. 검토결과로부터 발견된 문제점들은 HED (Human Engineerign Discrepance) 목록으로 정리하여 설계에 반영하도록 하였다.로 마음의 안정감, 몸의 긴장 이완에 따른 건강 상태 유지, 수업 집중도 향상 등이 나타났다. 위와 같은 종합 적 분석 결과에 따라, 본 연구는 제조 현장의 생산성 향상 및 품질 향상과 연계하여 작업자의 작업 집중도 향상, 작업자의 육체적, 심리적 변화에 따른 생산성 및 품질 향상 변화 정도 등의 산업공학(인간공학) 제 분야의 여러 측면에서 연구 및 적용이 가능하리라 사료된다.l, 시험군:25.90$\pm$7.16mg/d1, 47% 감소)를 나타내었으며, 시험군의 AUC는 대조군에 비해 39% 감소하였고, 혈중 아세트알데히드의 농도는 투여 60분후 시험군(3.96$\pm$0.07nmo1/$m\ell$)이 대조군(6.45$\pm$0,64nmo1/$m\ell$)에 비해 유의성 있는 감소(39%)를 나타내었으며, 시험군의 AUC는 대조군에 비해 48% 감소하였다 한편, 시험관내 에탄올 대사 효소에 대한 바이오짐의 효과를 검색해본 결과 바이오짐(2.0 $\mu\textrm{g}$/assay)에 의해 Aldehyde dehydrogenase(1.5unit/assay)의 활성이 14% 증가되었다. 본 연구의 결과로 볼 때, 비지니스 및 바이오짐은 음주 후 상승된 혈중 에탄을 농도 및 아세트알데히드의 농도를 현저히 감소시키는 효과가 있었다.량 보호 관리, 도시 소공원 개발, 역사 문화 공원 조성, 하천 공간 복원, 공원 시설 기능 개선, 이용 프로그램 개발, 공원 관리 개선, 환경 피해 녹지의 회복, 도시 환경 림 조성, 녹지 기능 증진, 도시 자연 경관 보전, 공원 녹지체계 구성, 공원 녹지 공급 균형, 주변 환경 녹화, 가로 녹화의 17개 시책을 제안하였다. 이러한 정책사업의 원활한 추진을 위해서는 기존의 관주도의 일방적인 공원 녹지 행정이 아닌 시민의 참여를 통

• The Journal of the Korea Contents Association
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• v.8 no.11
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• pp.217-224
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• 2008

Is trend that treatment that use isotope of radioactive substance increases from 1964 to now steadily. Bursting tube state solidified accordingly. But, do not establish treatment ward in presence at a sickbed by means that present regulation and system escape this as well as possession that exert negative impact in treatment action preferably is and is treating by radioactivity of small quantity, treatment air by that do not detain many sickers without equaling the institution although there is treatment ward keeps fair death anniversary and is in reservation stand-by status. To possess about 10 therapy rooms including existing sickroom in the institute of nuclear energy recently is looked but is waiting for an opportunity for treatment during suitableness time yet indeed even as that operate 57 radiation isotope therapy rooms all in about 28 hospitals in present domestic state is solveded. Therefore, radiation safety supervision by medical treatment action that treat as radioactive substance may need more active effort. Make mandatory to equipment that hospital which correspond to present the third medical examination and treatment must equip, or effort about more active system improvement may have to be about equipment that enforce this.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.11 no.3
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• pp.229-243
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• 2013

An in situ solute migration system was designed and installed in KAERI Underground Research Tunnel (KURT) constructed in the site of Korea Atomic Energy Research Institute (KAERI) in order to investigate the migration and retardation of non-sorbing and sorbing tracers through a rock fracture. The system is composed of three main parts including injection, extraction, and data treatment. For the selection of a water-conducting fracture, boreholes were drilled. The fractures in the drilled boreholes were investigated using borehole image analysis using borehole image processing system (BIPS). The results of BIPS analysis showed that borehole YH 3-1 and YH 3-2 were connected each other. Moreover, hydraulic tests were carried out to determine the test section with connectivity for the in situ experiments. The in situ solute migration experiments were accomplished to understand the migration of solutes through fractures in KURT using non-sorbing tracers which were fluorescein sodium, eosin-B, bromide and sorbing tracers which were rubidium, nickel, zirconium, and samarium.

• Journal of Radiation Protection and Research
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• v.21 no.3
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• pp.155-166
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• 1996

All nuclear facilities and components should receive an initial ALARA review before the installation and thereafter whenever modifications are planned. A major objective in design aspects of ALARA is to identify areas where specific engineering input can reduce personnel exposure. The basic factors which should be considered in the ALARA design review process include curd control, shielding and isolation of radiation sources accessibility maintainability and reliability, and contamination control. Because many diverse aspects must be considered in the ALARA design reviews, a proper ALARA checklist should be used to aid the designer in preventing any of the ALARA review considerations from being slipped away. In order to develop the practical ALARA checklist, check items for basic ALARA factors have been prepared, and what should be considered in reviewing each item has been discussed here. Based on the proposed factors and items, an ALARA checklist was developed.

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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• 2013.05a
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• pp.1017-1019
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• 2013

The radiation sources leaked from large-scale radiation leak accident like the Hukushima nuclear power plant accident or nuclear explosions can cause to the very large damage for us. So that the damage can be minimized, we have being developed a detector that can providing information about the location of the source to remove dangerous substances quickly than the conventional single detector. In this paper, we designed the shielding and collimator for the development of the Stereo Radiation detector in order to detect contaminants using MCNP Code. And we analyzed the results that is detected from the discretionary position of the radiation source. The results of this paper will be used as the basis for designing efficient structure for the radiation detectors.