• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2006년도 학술논문요약집
• /
• pp.156-157
• /
• 2006

• 한국방사성폐기물학회:학술대회논문집
• /
• 한국방사성폐기물학회 2006년도 학술논문요약집
• /
• pp.158-159
• /
• 2006

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 2005년도 추계학술발표회
• /
• pp.448-449
• /
• 2005

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 2005년도 춘계학술발표회
• /
• pp.1231-1232
• /
• 2005

• 한국환경생태학회지
• /
• 제14권1호
• /
• pp.38-45
• /
• 2000

강원도 고성군 죽왕면과 토성면 일대의 소나무군락을 대상으로 1996년 4월에 발생한 산화에 따른 산림환경변화가 토양의 이화학성에 미치는 영향을 구명하기 위하여 비산화지역(NF) 산화후 비벌채지역(FNC), 산화후 벌채지역(FC) 및 산화후 조림지역(FCP)으로 분류하여 토양의 특성을 분석하였다. 전조사지역의 토성은 사질식양토이었고, 토양의 입경조성을 비교하면 비산화지역은 표토의 모래함량이 심토보다 낮았고, 점토함량은 높았지만 산화지역은 모두 표토의 모래함량이 점토에 비해 높았다. 토양공극 분포 중 전공극량은 지역별로 큰 차이가 없었으나, 조공극량과 투수성은 비산화지역 ＞ 산화후 비벌채지역 ＞ 산화후 조림지역 ＞ 산화후 벌채지역 순이었고, 세공극량과 가비중은 반대의 경향을 나타내었다. 이는 산화에 따른 산림환경변화로 지피식생이 제거되어 토양침식이 가속화되면서 토양 내 수분함유능력의 지표인 토양공극과 투수성에 큰 영향을 주면서 토양물리성을 악화시키고 있는 것으로 판단된다. 토양 pH는 비산화지역과 산화후 비벌채지역이 산화후 벌채지역과 조림지역보다 표토 및 심토 모두 높게 나타났다. 유기물함량 및 전질소함량 변화는 표토와 심토 모두 비산화지역＞ 산화후 비벌채지역＞ 산화후 조림지역＞ 산화후 벌채지역 순이었다. 양이온치환용량 및 치환성 양이온($K^{+}$ , $Na^{+}$ /, $Ca^{2+}$, $Mg^{2+}$)함량 변화는 모두 표토가 심토보다 높았으며, 지역별로는 비산화지역＞ 산화후 비벌채지역＞ 산화후 조림지역＞ 산화후 벌채지역 순으로, 이는 산화후 표토층의 침식으로 지력이 악화된 결과로 사료된다.

• Nuclear Engineering and Technology
• /
• 제55권9호
• /
• pp.3183-3193
• /
• 2023

The water radiolysis in-core at light water reactors (LWRs) produces various radicals with other ionic species/molecules and radioactive nitrogen species in the reactor coolant. Nitrogen species can exist in many different chemical forms and recirculate in water and steam, and consequently contribute to what extent the environmental safety at nuclear power plants. Therefore, a clear understanding of formation kinetics and chemical behaviors of nitrogen species under irradiation is crucial for better insight into the characteristics of major radioactive species released to the main steam or relevant coolant systems and eventually development of advanced processes/methodologies to enhance the environmental safety at nuclear power plants. This paper thus focuses on basic principles on electrochemical interaction kinetics of radiolytic molecules and various nitrogen species in high temperature water, fundamental approaches for calculating thermodynamic values to predict their stability and domain in LWRs, and the effect of nitrogen species on crevice chemistry/corrosion and intergranular stress corrosion cracking (IGSCC) susceptibility of structure materials in high temperature water.

• 식품과학과 산업
• /
• 제54권4호
• /
• pp.268-277
• /
• 2021

A geographical indication (GI) is a sign used on products that have a specific geographical origin and possess qualities or a reputation that are due to that origin. This paper explores ways to protect Korean goods as GIs in the U.S. and EU by examining the efforts of the Colombian Coffee Federation (FNC) to protect Colombian coffee. The FNC enhanced the global awareness of Colombian coffee and increased the profits of Colombian coffee producers by registering Colombian coffee as a certification mark in the U.S. and as a GI under the EU's quality schemes. The Korean government protects kimchi under its own GI system. For kimchi products to earn the label "Korean kimchi," the three main ingredients must be produced in Korea. This has been a challenge for kimchi producers, who often rely on imported ingredients. Korea could learn from FNC's strategies to improve the current GI system for kimchi.

• 시스템엔지니어링학술지
• /
• 제10권1호
• /
• pp.49-56
• /
• 2014

Since steam generator (SG) tubes are located in the boundary between the primary and secondary systems of nuclear power plant (NPP), the SG is one of the most important components in the aspects of the safety of NPP. The magnetite ($Fe_30_4$) deposition, so-called fouling, is generally known as a major aging mechanism of CANDU SGs, and this aging mechanism makes the heat transfer efficiency between the primary and secondary systems of NPP reduced. Therefore, the development of SG safety assessment system which can evaluate the effect of the SG aging degradation mechanism should be needed for safety of NPP. In this study, through the suggestion of the guideline for SG safety assessment, it is possible to strengthen the basic of establishing the effective SG aging management technique. The SG safety assessment is carried out by CATHENA(Canadian Algorithm for THErmalhydraulic Network Analysis). It is possible to determine the integrity of SGs by identifying the main safety parameters which can be changed by the aging degradation of CANDU SGs.

• Nuclear Engineering and Technology
• /
• 제49권4호
• /
• pp.692-699
• /
• 2017

The determination of the shape and rising velocity of gas bubbles in a liquid pool is of great importance in analyzing the radioactive aerosol emissions from nuclear power plant accidents in terms of the fission product release rate and the pool scrubbing efficiency of radioactive aerosols. This article suggests a simple parameterization for the gas bubble rising velocity as a function of the volume-equivalent bubble diameter; this parameterization does not require prior knowledge of bubble shape. This is more convenient than previously suggested parameterizations because it is given as a single explicit formula. It is also shown that a bubble shape diagram, which is very similar to the Grace's diagram, can be easily generated using the parameterization suggested in this article. Furthermore, the boundaries among the three bubble shape regimes in the $E_o-R_e$ plane and the condition for the bypass of the spheroidal regime can be delineated directly from the parameterization formula. Therefore, the parameterization suggested in this article appears to be useful not only in easily determining the bubble rising velocity (e.g., in postulated severe accident analysis codes) but also in understanding the trend of bubble shape change due to bubble growth.

• Nuclear Engineering and Technology
• /
• 제55권5호
• /
• pp.1830-1837
• /
• 2023

The thermal cutting of contaminated or activated metals during decommissioning nuclear power plants inevitably results in the release of radioactive aerosol. Since radioactive aerosols are pernicious particles that contribute to the internal dose of workers, air conditioning units with a HEPA filter are used to remove radioactive aerosols. However, a HEPA filter cannot be used permanently. This study evaluates the efficiency and lifetime of filters in actual metal cutting condition using a plasma arc cutter and a high-resolution aerosol detector. The number concentration and size distribution of aerosols from 6 nm to 10 ㎛ were measured on both the upstream and downstream sides of the filter. The total aerosol removal efficiency of HEPA filter satisfies the standard of removing at least 99.97% of 0.3 ㎛ airborne particles, even if the pressure drop increases due to dust feeding load. The pressure drop and particle size removal efficiency at 0.3 ㎛ of the HEPA filter were found to increase with repeated cutting experiments. By contrast, the efficiency of used HEPA filter reduced in removing nano-sized aerosols by up to 79.26%. Altogether, these results can be used to determine the performance guidance and replacement frequency of HEPA filters used in nuclear power plants.