• 대한방사선방어학회:학술대회논문집
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• 2011.11a
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• pp.162-163
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• 2011

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.1
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• pp.107-120
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• 2019

The decommissioning of one nuclear power plant in a multi-unit nuclear power plant (multi-unit NPP) site may pose radiation exposure risk to decommissioning workers. Thus, it is essentially required to evaluate the exposure dose of decommissioning workers of operating multi-unit NPPs nearby. The ENDOS program is a dose evaluation code developed by the Korea Atomic Energy Research Institute (KAERI). As two sub-programs of ENDOS, ENDOS-ATM to anticipate atmospheric transport and ENDOS-G to calculate exposure dose by gaseous radioactive effluents are used in this study. As a result, the annual maximum individual dose for decommissioning workers is estimated to be $2.31{\times}10^{-3}mSv{\cdot}y^{-1}$, which is insignificant compared with the effective dose limit of $1mSv{\cdot}y^{-1}$ for the public. Although it is revealed that the exposure dose of operating multi-unit NPPs does not result in a significant impact on decommissioning workers, closer examination of the effect of additional exposure due to actual demolition work is required. The calculation method of this study is expected to be utilized in the future for planned decommissioning projects in Korea. Because domestic NPPs are located in multi-unit sites, similar situations may occur.

• Proceedings of the ESK Conference
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• 1994.04a
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• pp.147-156
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• 1994

국내에는 다수 원자력발전소가 가동중이며 국내기술진의 참여로 건설되고 있는 원전도 있는데, 그중 영광 3호기가 앞으로 건설될 원자력발전소의 원형으로 주목받고 있다. 원자력발전소에서 주제어반 (MCB: Main Control Board)은 운전원과 계통간의 상호작용이 이루어지는 핵심시설로써, 원자력발전소의 안전성과 효율성에 미치는 영향이 큰 것으로평가되어 인간공학적인 측면이 강조되고있다. 본문은 영광 3호기의 주제어반 시설검사에 참여한 결과를 주제어반 설계에 대한 인간공학적 평가의 예비보고로써 제시하고자 한다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05a
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• pp.520-526
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• 1997

WASH-1400[1]이 발간된 이후 수행되어왔던 많은 확률론적 안전성 평가 결과를 보면 노심손상빈도를 나타내는 사고경위 중 많은 부분이 인간행위와 관련이 있는 것으로 밝혀져 확률론적 안전성 평가에서 인간행위를 다루는 것은 매우 중요하게 되었다. 그러나 인간신뢰도분석은 인간행위의 다변성(variability)으로 인해 인간행위의 모델링이 어렵고 데이타가 부족해 뚜렷한 방법론이 없어 분석시 분석자의 주관성이 개입될 여지가 있고 분석결과에는 많은 불확실성을 포함하고 있다. 노심손상빈도를 나타내는 사고경위에는 다수 인간행위가 있는 포함돼있는 단절집합을 얻게되는데 이러한 인간행위들 사이에는 기기의 공통원인 고장처럼 의존성이 존재한다. 이러한 의존성의 평가방법 또한 뚜렷하게 설정되어 있지 않은 형편이다. 이에 본 논문에서는 월성 2,3,4호기 확률론적 안전성 평가 모델에 고려되어있는 인간행위들의 인간오류 확률 값과 의존성 수준의 변화에 대한 민감도분석을 수행하였다. 분석결과 초기사건 이후의 인간행위가 노심손상빈도 변화에 크게 기여하는 것이 밝혀졌고, 다수 인간행위들 사이의 의존성 수준변화가 노심손상빈도 변화에 큰 영향을 준다는 것이 밝혀졌다.

• Proceedings of the Korean Institute of Industrial Safety Conference
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• 2002.11a
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• pp.69-74
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• 2002

원자력발전소에서 발생하는 화재사건은 원자로 정지를 유발함과 통시에 안전정지 또는 사고완화 기능을 수행하는 다수의 기기를 동시에 손상시킬 수 있어 원자력발전소의 안전성에 적지 않은 영향을 줄 수 있다. 미국에서는 1975년 Browns Ferry 원전 1호기 케이블 포설실(cable spreading room)의 케이블 관봉투 밀봉재에 대한 건전성을 검사하는 과정 중에 화재가 발생하여 원자로 건물로 화재가 확산되는 심각한 사고가 발생하였다.(중략)

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.16 no.1
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• pp.107-122
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• 2018

Kori unit 1, the oldest commercial nuclear power plant in South Korea, was permanently shut down in June 2017. There are a lot of things to consider in decommissioning nuclear power plants, and one of them is the radiological environmental impact assessment. Performed to promote the health and safety of residents around the nuclear power plant, radiological environmental impact assessment aims to confirm that off-site radiological dose from radioactive material released from the facility does not exceed the regulatory criteria. There are three main parts of environmental impact assessment: pre-decommissioning environmental monitoring, environmental monitoring during decommissioning, and impact on nearby residents. At present, although the Korea Nuclear Safety Act stipulates that radiological environmental impact assessment resulting from decommissioning should be carried out, the details have not been specified. Therefore, this paper compares and analyzes guidelines for evaluation of radiological environmental impacts of nuclear power plants overseas, and presents a draft on the assessment of radiological dose resulting from decommissioning according to the Korean situation.

• Journal of the Earthquake Engineering Society of Korea
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• v.15 no.2
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• pp.43-51
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• 2011

Probabilistic seismic hazard analysis (PSHA), which can effectively apply inevitable uncertainties in seismic data, considers a number of seismotectonic models and attenuation equations. The calculated hazard by PSHA is generally a value dependent on peak ground acceleration (PGA) and expresses the value as an annual exceedance probability. To represent the uncertainty range of a hazard which has occurred using various seismic data, a hazard curve figure shows both a mean curve and percentile curves (15, 50, and 85). The percentile performs an important role in that it indicates the uncertainty range of the calculated hazard, could be calculated using various methods by the relation of the weight and hazard. This study using the weight accumulation method, the weighted hazard method, the maximum likelihood method, and the moment method, has calculated the percentile of the computed hazard by PSHA on the Shinuljin 1, 2 site. The calculated percentile using the weight accumulation method, the weighted hazard method, and the maximum likelihood method, have similar trends and represent the range of all computed hazards by PSHA. The calculated percentile using the moment method effectively showed the range of hazards at the source which includes a site. This study suggests the moment method as effective percentile calculation method considering the almost same mean hazard for the seismotectonic model and a source which includes a site.

• KOREAN JOURNAL OF CROP SCIENCE
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• v.48 no.3
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• pp.243-247
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• 2003

To examine ideal leaf types with higher $\textrm{CO}_2$ assimilates and different seed sizes, 12 soybean varieties were planted on the pot in a plastic house covered with glass. Leaf function based on stomatal conductance and $\textrm{CO}_2$ assimilation in soybean is different in seed size and leaflet shape. Mean $\textrm{CO}_2$ assimilation of a single leaf was 19.66 $\mu\textrm{molm}^{-2}\textrm{s}^{-1}$ and showed higher in small seed cultivars with narrow leaflet than that of small seeds with wide leaflet (18.29 $\mu\textrm{molm}^{-2}\textrm{s}^{-1}$), but within large seed groups, it was higher in wide leaflets (19.17 $\mu\textrm{molm}^{-2}\textrm{s}^{-1}$) than narrow leaflet cultivars (17.45 $\mu\textrm{molm}^{-2}\textrm{s}^{-1}$). In small seed and narrow leaflet cultivars, stomatal conductance ranged from 0.14 to 0.15 $\mu\textrm{molm}^{-2}\textrm{s}^{-1}$, while $\textrm{CO}_2$ assimilation ranged from 19 to 20 $\mu\textrm{molm}^{-2}\textrm{s}^{-1}$. The Photosynthetic rate was closely related to stomatal conductance, transpiration and water use efficiency.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.14 no.4
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• pp.423-434
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• 2016

The importance of severe nuclear accidents and probabilistic safety assessment (PSA) were brought to international attention with the occurrence of severe nuclear accidents caused by the extreme natural disaster at Fukushima Daiichi nuclear power plant in Japan. In Korea, studies on level 3 PSA had made little progress until recently. The code systems of level 3 PSA, MACCS2 (MELCORE Accident Consequence Code System 2, US), COSYMA (COde SYstem from MAria, EU) and OSCAAR (Off-Site Consequence Analysis code for Atmospheric Releases in reactor accidents, JAPAN), were reviewed in this study, and the disadvantages and limitations of MACCS2 were also analyzed. Experts from Korea and abroad pointed out that the limitations of MACCS2 include the following: MACCS2 cannot simulate multi-unit accidents/release from spent fuel pools, and its atmospheric dispersion is based on a simple Gaussian plume model. Some of these limitations have been improved in the updated versions of MACCS2. The absence of a marine and aquatic dispersion model and the limited simulating range of food-chain and economic models are also important aspects that need to be improved. This paper is expected to be utilized as basic research material for developing a Korean code system for assessing off-site consequences of severe nuclear accidents.

• Journal of Animal Environmental Science
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• v.18 no.2
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• pp.99-110
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• 2012

The purpose of the study is to collect basis data for to establish standard administrative processes of liquid fertilizer treatment. From this survey we could make out the key point of each step through a case of effective liquid manure treatment system in pig house. It is divided into six step; 1. piggery slurry management step, 2. Solid-liquid separation step, 3. liquid fertilizer treatment (aeration) step, 4. liquid fertilizer treatment (microorganism, recirculation and internal return) step, 5. liquid fertilizer treatment (completion) step, 6. land application step. From now on, standardization process of liquid manure treatment technologies need to be develop based on the six steps process.