• Journal of Radiation Protection and Research
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• v.38 no.3
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• pp.143-148
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• 2013

Operational nuclear facilities such as nuclear power plants and particle accelerators show various neutron spectra according to the type of facilities and specific position. Necessities of neutron dose management and neutron monitoring for radiation protection of radiation workers in such a kind of facilities have continuously increased in recent years. Bonner sphere spectrometers are widely used for measurement of neutron spectra. Data on response function of neutron detector, default neutron spectra and count rates of Bonner sphere spectrometer are required to obtain unfolded neutron spectra in specific workplaces. In this study, we carried out measurement of neutron spectra produced in MC50 cyclotron using Bonner sphere spectrometer with LiI scintillation detector. Additionally, we estimated quantitative data on neutron flux, mean neutron energy and ambient dose equivalent rate according to the incident proton energies and positions in MC50 cyclotron.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.2
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• pp.117-123
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• 2012

In order to dispose of the LILW(low and intermediate level radioactive waste) stored at KAERI, the radwaste drum assay system will be introduced to evaluate the radioisotopes inventory of stored drums. At present, the construction project of the dedicated assay facility to operate it and carry out routine maintenance of that equipment has been conducting at the radwaste treatment facility. Since that facility will be constructed in front of a 1st radwaste storage facility as well as the radwaste drums to be assayed and the transmission source in the radwaste drum assay system are in that facility, they could act as the radioactive sources and then, would affect the dose rate at the inside and the outside of the facility. Therefore, the radiation shielding should be evaluated through the concrete wall near to the radioactive sources whether the wall thickness is sufficient against the regulations. In this study, the radiation safety for the concrete wall around the radiation controlled area in the radwaste drum assay facility was evaluated by the MCNP code. From the evaluation results, the thickness of those concrete walls which are under consideration of about 30 cm was enough to shield the radiation from the radioactive sources.

• Nuclear Engineering and Technology
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• v.2 no.2
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• pp.97-106
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• 1970

Radiation accidents which occured in the A.E.R.I. during last ten years are described (table 1). It seemed to the authors that some of these accidents were considered to be hazardous to man body and associated installations. This report deals with the following four major accidents involving body contamination incidents that our health physicists have been experienced. 1. Over-exposures (up to 130 rem) to the total body due to the mismanipulation in the Cobalt-60 gamma irradiation facility. 2. Floor surface contamination (up to 13 mrad/hr) and its spread out due to the mishandling of radioiodine contained in the bottle. 3. Body surface contamination and 0.36 uCi radioactivity accumulated in the thyroid gland of a worker due to the inhalation of gaseous iodine-131. 4. A void capsule due to the leakage out of the radium therapeutic source (3mg\ulcorner) These accidents were treated by definitely prompt action to protect the workers and associated installations from any radiation hazards and every possible efforts were made to confine the spread of radioactive contamination as small area as possible by means of elaborate decontamination work and monitoring.

• Proceedings of the Korea Information Processing Society Conference
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• 2014.04a
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• pp.807-810
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• 2014

로봇 시스템의 제어 및 이를 이용한 환경 인식에는 많은 전자 광학 소자들이 사용되고 있다. 로봇 제어회로에 사용되고 있는 Si CMOS 공정의 CPU, ASIC, FPGA 소자는 고 선량의 감마선에 취약하다. 환경정보 수집용으로 로봇에 탑재되는 CMOS/CCD 카메라의 관측영상에는 고선량 감마선으로 인한 speckle (백색잡음, white noise) 들이 나타나며, 이들이 카메라의 관측성능을 저하시킨다. 후쿠시마 원자력발전소 사고와 같이 원자력시설에서 제어불능의 심각한 사고가 발생되면 고선량 감마선이 방출된다. 이러한 고선량 감마선방출은 사람에 의한 사고수습을 불가능하게 하며, 사고 수습을 위해서는 로봇의 활용이 불가피하다. 그러나, 방출되는 고선량 감마선의 세기(선량율)가 지나치게 높을 경우, 로봇 전자회로가 장애를 일으키기 때문에 로봇의 적절한 임무수행이 가능한 감마선 세기에 대한 고려가 필요하다. 본 논문에서는 고선량 감마선 환경하에서의 로봇 탑재 CCD/CMOS 카메라의 관측 성능을 고려하여 100 Gy/h 를 감마선 선량율 제한조건으로 설정한다. 그리고, 재 가동 승인심사를 받기 위해 일본의 원전 운영자들이 제시한 PWR (가압경수로) 원전의 중대사고 대책 적합성 평가문서에 나타난 노심용융개시 시점의 원자로 격납건물내 감마선 선량율 추이 계산결과를 활용하여 로봇의 대응시간을 계산하였다. 문서 (PDF) 에 표현된 감마선 선량율 추이 그래프를 영상 판독하여, 격납건물내 감마선 선량율이 100 Gy/h 제한조건에 도달하는 시간을 계산하였다. 이를 로봇의 대응시간으로 설정한다.

• Proceedings of the Korea Water Resources Association Conference
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• 2017.05a
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• pp.551-551
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• 2017

우리나라와 동아시아는 경제 성장에 따른 전력수요가 크게 증가하였으며, 증가하는 대부분의 전력수요를 원자력으로 대체하고자 원전을 통한 전력생산 비중을 증가시키고 있다. 현재 중국은 13기의 원전을 가동 중이며, 동남 해안지대에 집중되어 있다. 또한, 건설 중인 원전은 27기로 전세계에서 건설 중인 원전의 41%를 차지한다. 원전의 증가에 따른 방사능 누출에 대한 위험성 역시 증가되고 있는 실정이다. 한국원자력안전기술원에서 중국 중서부지역에서 방사능이 누출될 경우 방사성 물질이 한반도로 이동하는 모의 상황에 대한 시뮬레이션을 통해, 원전 사고 발생 시 사흘 만에 제주도를 포함한 대한민국 전역이 방사성 물질로 뒤덮이는 것으로 분석하였다. 중국에서 누출된 방사성물질은 편서풍을 타고 한반도로 이동하게 되며, 일부는 낙진으로 유역 또는 하천에 유입되고 일부는 동해를 지나 일본으로 이동 할 것이다. 그동안 중국에서의 방사능 누출사고를 통한 방사성물질의 국내유입에 의한 영향에 대한 연구가 부족한 것이 현실이다. 이에 본 연구에서는 중국 텐완에서 원전사고 발생시 국내 하천에 어떠한 영향을 미치는지 분석하고자 환경다매체 모형을 이용하여 방사성물질(세슘, Cs-137)의 영향에 대한 모의를 진행하였다. 중국 텐완원전에서 방사성 Cs-137이 누출되어 춘천지역에 도달하였을 때의 대기중 농도 $5,650Bq/m^3$로 가정하여 모의 시나리오를 구성하였다. 모의 지역은 북한강 수계를 대상으로 하였으며, 7개의 중권역과 549.3 km의 하천이 포함되었다. 다매체 모형 모의를 통해 방사성물질 낙진으로 인한 Cs-137이 북한강 수계에 어떠한 영향을 미치는지 알아보고자 북한강수계의 팔당댐 부근의 오염농도를 모의하였다. 우리나라의 원자력시설 방호 방재법에 따른 상수원 취수기준(먹는물)은 100 Bq/L로 되어있다. 본 연구의 시나리오 모의결과, 모의 1일차에서 45 Bq/L, 모의 8일차에는 먹는물 기준 100 Bq/L를 초과하여 최대 119.56 Bq/L로 오염되는 것으로 모의되었다. 따라서, 반감기가 큰 방사성물질을 유입으로 오염된 하천은 개선하기 위해서는 오랜 시간과 높은 처리비용이 발생되기 때문에 인접국 또는 국내의 방사능 누출로 인한 상수원 오염 발생에 대비한 초기/중 장기적인 대응책 마련이 필요한 시점이다.

• Proceedings of the KAIS Fall Conference
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• 2012.05a
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• pp.452-454
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• 2012

본 논문에서는 열분해 및 촉매반응의 의한 Hydrazine의 Ammonia 전환율을 연구하였다. 원자력발전소 2차 계통은 물/증기 순환계통으로 기기 및 배관의 부식을 억제하고, 증기발생기(Steam Generator, SG)의 부식생성물 유입을 최소하기 위해 전휘발성처리법(All Volatile Treatment, AVT)을 적용하여 계통수의 pH를 약염기성으로 유지하고 있다. 또한 Hydrazine을 이용하여 계통수의 용존산소제거 및 환원성 분위기를 유지하고 있다. 현재 사용되는 AVT는 대부분 단일 아민(Ammine)으로 계통 전 영역에서 pHt를 약염기성으로 유지하기 어렵다. 따라서 복합 아민을 이용하여 단일 아민의 상호단점을 보완한 수처리법을 적용해야한다. 하지만 복합 아민을 적용할 경우 추가 아민 주입설비, 설치부지, 시설유지보수 및 관리가 요구되므로 기존 주입약품을 이용하여 아민을 공급할 수 있는 연구가 필요하다. 따라서 본 연구에서는 Hydrazine의 열분해 및 촉매반응을 이용한 Ammonia 전환율을 조사하였다.

• The Journal of Engineering Geology
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• v.19 no.1
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• pp.63-70
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• 2009

The optical fiber cable acting as a sensor was embedded in the underground research tunnel and portal area in order to monitor their stability and the spatial temperature variation. This system includes two types of sensing function to monitor the distributed strain and temperature along the line, where sensor cable is installed, not a point sensing. According to the results of one year monitoring around the KURT, there is no significant displacement or movement at the tunnel wall and portal slope. However, it would be able to aware of some phenomena as an advance notice at the tunnel wall which indicates the fracturing in rockmass and shotcrete fragmentation before rock falls accidently as well as movement of earth slope. The measurement resolution for rock mass displacement is 1 mm per 1 m and it covers 30 km length with every 1m interval in minimum. In temperature, the cable measures the range of $-160{\sim}600^{\circ}C$ with $0.01^{\circ}C$ resolution according to the cable types. This means that it would be applicable to monitoring system for the safe operation of various kinds of facilities having static and/or dynamic characteristics, such as chemical plant, pipeline, rail, huge building, long and slim structures, bridge, subway and marine vessel. etc.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.8 no.4
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• pp.293-301
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• 2010

Optical fiber cable, as a sensor, was installed on the wall of KAERI(Korea Atomic Energy Research Institute) Underground Research Tunnel(KURT) in order to monitor the physical stability of the tunnel, which was constructed for technical development and demonstration of radioactive waste disposal. This monitoring system has two simultaneous measurements of temperature and strain over time using Brillouin backscatter. According to the results of the monitoring from Jan. 2008 to Nov. 2009, there is no significant displacement or movement at the tunnel wall However, the cumulative volume of total strain increased slightly as time passes with the comparison of the reference observation, which was measured in Jan. 2008. The change in cumulative volume of total strain indicates that the strain level had been affected by saturation and de-saturation phenomena due to groundwater fluctuation at several points at KURT. This system is based on the distributed sensing technique concept, not point sensing. By using this system, a displacement can be detected with the range from $20{\mu}{\varepsilon}$ to $28,000{\mu}{\varepsilon}$ every 1m interval in minimum. A temperature variation can be monitored at every 0.5m interval with the resolution of 0.01 in minimum. Based on the study, this monitoring system is potentially applicable to long term monitoring systems for radioactive waste disposal project as well as other structures and underground openings.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.3
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• pp.199-208
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• 2012

To develop site characterization technologies for a radioactive waste disposal research in KAERI, the geological and hydrogeological investigations have been carried out since 1997. In 2006, the KURT (KAERI Underground Research Tunnel) was constructed to study a solute migration, a microbiology and an engineered barrier system as well as deeply to understand geological environments in in-situ condition. This study is performed as one of the site characterization works around KURT. Several investigations such as a lineament analysis, a borehole/tunnel survey, a geophyscial survey and logging in borehole, were used to construct the geological model. As a result, the geological model is constructed, which includes the lithological model and geo-structural model in this study. Moreover, from the results of the in-situ hydraulic tests, the hydrogeological properties of elements in geological model were evaluated.

• Explosives and Blasting
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• v.27 no.1
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• pp.21-31
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• 2009

An excavation damaged zone (EDZ) is created by fracturing, excavation or stress redistribution of tunnels. In this zone the mechanical and hydraulic properties of rock are changed, which makes additional cracks and serves as a dominant pathway of groundwater flow. In this study, an assessment on an EDZ size was practiced by the measurement of the deformation modulus at the KAERI underground research tunnel (KURT), and the information was applied to the modelling analysis using FLAC2D software. The EDZ at KURT fell into the range of 0.6~1.8m and the deformation moduli of the EDZ generally correspond to about 40% of intact rock mass. With a consideration of the EDZ in numerical analysis, tunnel displacements increased by about 65% and the maximum principal stress decreased to 58% from the case without EDZ. The plastic zone of the tunnel was enlarged to the crown and invert zones of the tunnel within the range of the length of rock bolts. About 2% of the total tunnel displacement with EDZ was suppressed by the KURT support system. It is anticipated that the investigation of an EDZ can be used as an important and fundamental research for validating the overall performance of a high level waste disposal system.