• Journal of Sensor Science and Technology
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• v.24 no.2
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• pp.96-100
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• 2015

In the present study, we developed a real-time radiation-monitoring sensor for an underwater radiation-monitoring system and evaluated its effectiveness using reference radiation sources. The monitoring sensor was designed and miniaturized using a silicon photomultiplier (SiPM) and a cerium-doped-gadolinium-aluminum-gallium-garnet (Ce:GAGG) scintillator, and an underwater wireless monitoring system was implemented by employing a remote Bluetooth communication module. An acrylic water tank and reference radiation sources ($^{137}Cs$, $^{90}Sr$) were used to evaluate the effectiveness of the monitoring sensor. The underwater monitoring sensor's detection response and efficiency for gamma rays and beta particles as well as the linearity of the response according to the gammaray intensity were verified through an evaluation. This evaluation is expected to contribute to the development of base technology for an underwater radiation-monitoring system.

• 제어로봇시스템학회:학술대회논문집
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• 1996.10b
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• pp.1372-1375
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• 1996

In this paper, we developed and ERMS, which monitors radiation continuously in the vicinity of the nuclear power plant not only to intend health and security of the adjacent residents but also to prevent environmental pollution. Especially, applying digital DCU and SCA which are easy to control and accurate, we obtained good results.

• Computational Structural Engineering
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• v.8 no.1
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• pp.13-18
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• 1995

원전의 주요 구조물은 극심한 재해를 초래할 수 있는 자연현상(지진, 쓰나미 등)이 수반하는 극한하중에 견딜 수 있어야 하고 내부의 안전관련 기기의 기능과 만일의 사고(주증기나 고에너지 배관파단사고)시에도 구조적 안전성이 보장되도록 설계.시공되고 있다. 또한 운전원의 조작실수나 오판을 극복할 수 있도록 원자로 고유의 안전성과 자연법칙에 의한 정상유지를 할 수 있는 신기술이 도입되고 있다. 품질보증 계획에 의한 최선의 품질보장, 엄격한 방사선 감시와 온배수 영향의 최소화, 최신방사성 폐기물 처분기술 적용 등을 통하여 기술의존형 에너지인 원자력의 활용증대가 불가피하다고 판단된다.

• Korean Journal of Agricultural and Forest Meteorology
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• v.23 no.4
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• pp.193-197
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• 2021

• Journal of the Korean Society of Radiology
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• v.5 no.6
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• pp.351-355
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• 2011

In this paper, monitoring system and platform of plant growth are suggested which are required by safe crop management about disaster and radiation pollution. In addition, by monitoring plant growth, the growth of plants that can measure the size of the efficient system was developed. The expected effect of this study, first, through natural disasters and radioactive contamination monitors produce fast and accurate response function can result in improved quality and productivity. Second, the size of the plant required to maintain the measurement data can save time and expense savings. Finally, plant managers can improve work efficiency.

• Journal of Radiation Protection and Research
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• v.30 no.3
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• pp.131-148
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• 2005

In a nuclear emergency, protective actions for the public should be taken in time. It is internationally proposed that generic intervention levels (GILs) and generic action levels, determined based on cost-benefit analyses, be used as the decision criteria for protective actions. Operational intervention levels (OILs) are directly or easily measurable quantities corresponding to these generic levels. To assess the necessity of protective actions in a nuclear emergency, it is important that the environmental monitoring data required for applying and revising OILs should be promptly produced. It is discussed what and how to do for this task in the course of the emergency response. For an emergency environmental monitoring to be performed effectively, a thorough preparedness has to be made including maintenance of the organization and equipments, establishment of various procedure manuals, development of a supporting computer system and periodical training and exercises. It is pointed out that Korean legal provisions concerning GILs and OILs need to be amended or newly established.

• Journal of Radiation Protection and Research
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• v.28 no.3
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• pp.255-261
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• 2003

An environmental radiation monitoring system based on high pressurized ionization chamber has been used for on-line gamma monitoring surrounding the KAERI (Korea Atomic Energy Research Institute), which transmits the dose data measured from ion chamber on the site via radio frequency to a central processing computer and stores the transmitted real-time data. Although communication using radio frequency has several advantages such as effective and economical transmission, storage, and data process, there is one main disadvantage that data loss during transmission often happens because of unexpected communication problems. It is possible to restore the loss data by off-line such as floppy disk but the simultaneous process and display of current data as well as the backup data are very difficult in the present on-line system. In this work, a new electronic circuit board and the operation software applicable to the conventional environmental radiation monitoring system are developed and the automatical synchronization of the ion chamber unit and the central processing computer is carried out every day. This system is automatically able to restore the backup data within 34 hours without additional equipments and also display together the current data as well as the transmitted backup data after checking time flag.

• Journal of Radiation Protection and Research
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• v.24 no.4
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• pp.225-230
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• 1999

This study was carried out to investigate the radiation dose-response of micronucleus frequencies in Tradescantia pollen mother cells. The number of micronuclei increased in the tetrads as a result of chromosome deletion after irradiation. The maximal frequency of micronuclei showed a good dose-response relationship in the range of dose $0{\sim}50$ cGy. On the basis of the relationship, a dose of 1 cGy results maximally in two additional micronuclei in 100 tetrads. The radiation dose-response relationship of micronucleus occurrence is prerequisite to biological monitoring of radiations. The micronucleus assay can be applied to biological risk assessment of environmental toxicants, and to integrity test of water or soils of interest.

• Journal of the Korean Society of Radiology
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• v.5 no.3
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• pp.155-159
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• 2011

The purposed of this study were measured the radiation exposure of patients and workers by generators, and the protection state for radiation facilities. The subject of the study by X-ray generators in university hospitals of capital area, we measured the maximum irradiation condition of 80 kVp, 200 mA, 0.1 second in the control entrance, control room window, entrance of radiography, adjacent site. The leakage dose per week was which the control entrance was 0.11 mR/week, control room window was 0.15 mR/week, entrance of radiography was 0.12 mR/week and adjacent site was 0.06 mR/week with X-ray unit the mean And the leakage mean dose was 0.11 mR/week. Diagnostic X-ray tubes must ensure that the leakage radiation in the maximum leakage dose in week emitted by the tube outside the useful beam does not exceed certain levels provided by standards.

• Journal of Radiation Protection and Research
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• v.37 no.4
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• pp.219-225
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• 2012

This study makes differentiated regulations which can maximize the efficiency and convenience of radiation safety regulations by deriving evidence required to establish reasonable safety regulatory structure based on the determination of the levels of actual radiation safety regulations for radiation safety managers to perform radiation safety. We surveyed approximately 10% of radiation safety managers from domestic radiation-using organizations which was based on the Nuclear Safety Act and NUREG Vol. 1~21 of RS-G-1.9 (2005), NRC of IAEA, etc. The radiation safety managers showed the highest level of awareness on the requirements for exposure management ($3.32{\pm}0.910$), and the lowest level on the requirements for record keeping and storage of documents ($2.84{\pm}0.826$). Industrial organizations showed higher levels of awareness than medical organizations whose regulations should be more stringent on requirements of the status and management of radioactive sources, facilities, measurements, pollution control, measuring equipment, monitoring, education and training, and exposure management. This suggests that the actual regulations need to be re-evaluated because it is attributed to the regulations which are statistically significant difference of the levels of radiation safety regulations between industrial organizations and medical organizations. The process of developing regulatory requirements for each characteristic of domestic organizations needs to be done in future studies, as well as safety regulations to maximize convenience should be achieved if radiation safety regulations are conducted in consideration with the characteristics of each organization.