• 건축역사연구
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• 제15권2호
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• pp.7-22
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• 2006

The Industrial Revolution brought a variety of new forms of structure, and as a group they are usually called 'industrial architecture'. Steam engines contributed greatly to architecture with a unique structure called 'water tower' to provide water for steam engines, especially the adoption of it. This study is to examine the changes of the building materials and architectural features of the water towers of railway stations built in the early twentieth century in South Korea. This study also attempts to describe the modern features of the industrial architecture, which did not get a chance to be noticed. Through this examination on water tower, which is a part of industrial architecture with sheer integration of function and pure geometric form, we would like to find the meaning of modern architecture in Korea. As we can see in the Korean oldest railway station water tower constructed in masonry at Yeonsan Station in 1911, early water towers were divided into the masonry machine room and the steel water tank. However, the masonry structure was soon turned into concrete structure with its formal features maintained as it was. The steel water tank was also replaced with concrete structure. As a result, while its basic structure remained, concrete structure had substituted for the every components of water tower. Concrete-built water towers were the high-tech architecture of that time and the most perfect structures built in concrete. Nevertheless, the perfection of the water tower form and the technology it attained were not transferred to other modern and contemporary architecture in South Korea. Since the subject to railway station water towers was the Japanese government, and steam engines were replaced with diesels in the midst of a complicated domestic situation after the independence, the need for water towers in railway stations disappeared and therefore, it became ignored and was difficult to look over the architectural features and values of early railway station water towers.

• 한국식품조리과학회지
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• 제5권2호
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• pp.35-41
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• 1989

This study was written to assess microbilogical quality by passage of time and holding method after making foods, by means of evaluating time, temperature and microbiological quality during vairous phases in product flow of hard-boiled mackerel served by an industry feeding operation for 500 persons a day, measuring pH & Aw and analyzing factors affecting nicrobiological growth conditions. The results were as fallows: 1. According to phases in product flow of hard-boiled mackerel, it showed 4.9 hours of mean of needed time, $27.5^{\circ}C$ of room temperature, 4.8~5.7 of pH value and 0.95~0.98 of Aw. these conditions were suitable for microbiological growth, and the phases with potential hygienic danger were pre-preparation and assembly & service. 2. As for holding methods and passage of time, holding as steam table was more effective than holding at room temperature as time past. 3. Food poisoning bacteria were not dectected from phases in product flow of hard-boiled mackerel.

• 한국건축시공학회지
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• 제18권5호
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• pp.439-446
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• 2018

PHC파일은 깊은 관입량과 지지력 보강이 유리한 말뚝기초공법으로 사용량이 지속적으로 증가하고 있다. 일반적으로 PHC파일을 제조할 경우 압축강도의 증진을 위해 고강도 혼합재를 주로 사용하지만, 최근에는 경제성을 고려하여 고로슬래그 미분말을 활용하는 연구가 진행되고 있다. 이에 본 연구에서는 고강도 혼합재 대신 고로슬래그 미분말의 치환율 및 양생조건을 고려한 PHC파일을 제조한 후 공학적 특성에 대해 검토하였다. 실험 결과, 고로슬래그 미분말을 치환한 PHC파일은 50, $80^{\circ}C$ (Steam curing) 양생조건에 의해 압축강도가 증가하며, 특히 $80^{\circ}C$ (Steam curing) 양생조건에서 고로슬래그 미분말을 20% 치환한 PHC파일은 약 84MPa의 압축강도를 나타내었다. 또한, $20^{\circ}C$ (Room temperature curing)의 양생조건에 비해 $80^{\circ}C$ (Steam curing) 양생조건에서 더 많은 수화생성물이 발생하는 것을 확인할 수 있으며, 이 때문에 조직이 치밀해지고, 압축강도 증가에 영향을 준 것으로 판단된다.

• 한국농촌건축학회논문집
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• 제14권3호
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• pp.17-24
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• 2012

This study is to propose the dwelling planning of collective housing for the senior citizen who lives alone in rural and fishing villages. and this paper analyzed a change element regarding the field of care service for the elderly. The results of research are as follows: First, the range a village unit of "Home for the Elderly" was investigated most primarily. Second, on the lifestyle of a bedroom, proper using person per a room was investigated to two people to use with one room and life style of using bed preferred more in life style of sitting on the floor(ondol). Third, most necessary facilities were examined into bathroom and steam-room, and the separation of man and woman space, toilet was investigated to 1 ranking. Fourth, to be most difficult care service was investigated by long-distance circulation. This is the item which can be reduced naturally in case of service activity caring for a visit in a collective housing.

• 한국윤활학회:학술대회논문집
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• 한국윤활학회 2001년도 제34회 추계학술대회 개최
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• pp.296-303
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• 2001

In nuclear power steam generators, high flow rates can induce vibration of the tubes resulting in fretting wear damage due to contacts between the tubes and their supports. In this paper the fretting wear tests and the sliding wear tests were performed using the steam generator tube materials of Inconel 690 against STS 304. Sliding tests with the pin-on-disk type tribometer were done under various applied loads and sliding speeds at air and water environment. Fretting tests were done under various vibrating amplitudes, applied normal loads and various temperatures. From the results of sliding and fretting wear tests, the wear of Inconel 690 can be predictable using the work rate model. Depending on normal loads and vibrating amplitudes, distinctively different wear mechanisms and often drastically different wear rates can occur. At room temperature, the wear coefficient K of Inconel 690 is 7.57${\times}$10$\^$13/Pa$\^$1/ in air and it is 1.93${\times}$10$\^$13/Pa$\^$1/ in water. At room temperature, it is found that the wear volume in air is more than in water. In water, the wear coefficient K at 50$^{\circ}C$ and 80$^{\circ}C$ is 4.35${\times}$10$\^$-13/Pa$^1$ and 5.81${\times}$10$\^$-13/Pa$^1$ respectively, Therefore, it is found that the wear volume extremely increases by increasing on temperature in water. This study shows that the dissolved oxygen with temperature increment increases and the wear due to fluidity is severe.

• Tribology and Lubricants
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• 제21권1호
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• pp.33-38
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• 2005

Fretting is the oscillatory motion with very small amplitudes, which usually occurs between two solid surfaces in contact. Fretting wear is the removal of material from contacting surfaces through fretting action. Fretting wear of steam generator tubes in nuclear power plant becomes a serious problem in recent years. The materials for the tubes usually are Inconel 690 (I-690) and Inconel 600 (I-600). In this paper, fretting wear tests for I-690 and I-600 were performed under various applied loads in water at room temperature. Results showed that the fretting wear loss of I-690 and I-600 tubes was largely influenced by stick-slip. The fretting wear mechanisms were the abrasive wear in slip regime and the delamination wear in stick regime. Also, I-690 had somewhat better wear resistance than I-600.

• Corrosion Science and Technology
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• 제8권3호
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• pp.126-131
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• 2009

The interaction between wear and corrosion can significantly increase total material losses in water chemistry environment. The corrosive wear tests of a PWR steam generator tube material (Alloy 690) against the anti vibration bar material (409 SS) were performed at room temperature. The tests were performed in alkaline water chemistry conditions. NaOH solution was selected for test condition to investigate the corrosive wear effect of steam generator tube material in alkaline pH condition without other factors. The flow induced vibration can caused tube damage and the corrosion can be occurred by water chemistry. The test results showed that, in the alkaline solution at pH 13.9, the corrosion current density was increased about ten times than that in the distilled water. And wear rate at pH 13.9 was increased about ten times from that at neutral condition. However, the wear rate was decreased with time. The decrease would be attributed to the change in roughness of specimen or sub-layer of the worn surface with time. From microstructure observation, severe abrasive shape and several wear debris were found. From those results, it could infer that the oxide film on Alloy 690 changed to easily breakable one in the alkaline water, and then abrasion with corrosion became the main wear mechanism.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.78-82
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• 2003

국내 원전에서 증기발생기 세정 후 발생되는 Fe-EDTA 함유 폐액 처리를 위한 초임계수 산화공정 (Supercritical Water Oxidation Process), 광촉매 산화 공정 (Photocatalyst Oxidation Process) 및 DBD 상온 플라즈마 공정 (Dielectric Barrier Discharge Atmospheric Pressure Plasma Process)이 평가되었다. 초임계수 산화 공정에 의해 99.98 %이상의 EDTA 전환율을 나타내어 EDTA 처리를 위한 효과적인 반응공정임을 확인하였으나 공정의 안정성, 부식 방지대책 등이 마련되어야 할 것으로 판단된다. 광촉매산화공정으로는 10 % 정도의 낮은 EDTA전환율을 보여 세정폐액 처리 공정으로는 부적합한 것으로 나타났다. DBD를 이용한 Methylene Blue 분해 결과 저 에너지 소비율로 높은 유기물 분해 효율을 얻을 수 있었으나 실 EDTA 공정에의 적용 및 공정 규모 확장 등에 대한 향후 연구 평가가 필요한 것으로 사료된다.

• Nuclear Engineering and Technology
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• 제51권5호
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• pp.1307-1313
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• 2019

Recent analysis results with realistic assumptions provide the variability of operator allowable time for the initiation of aggressive cooldown under small break loss of coolant accident or steam generator tube rupture with total failure of high pressure safety injection. We investigated how plant risk may vary depending on the variability of operators' failure probability of timely initiation of aggressive cooldown. Using a probabilistic safety assessment model of a nuclear power plant, we showed that plant risks had a linear relation with the failure probability of aggressive cooldown and could be reduced by up to 10% as aggressive cooldown is more reliably performed. For individual accident management, we found that core damage potential could be gradually reduced by up to 40.49% and 63.84% after a small break loss of coolant accident or a steam generator tube rupture, respectively. Based on the importance of timely initiation of aggressive cooldown by main control room operators within the success criteria, implications for improvement of emergency operating procedures are discussed. We recommend conducting further detailed analyses of aggressive cooldown, commensurate with its importance in reducing risks in nuclear power plants.

• 대한기계학회논문집A
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• 제35권8호
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• pp.951-956
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• 2011

원자력 발전설비의 증기발생기용 세관 재료로 인코넬 합금이 사용되고 있다. 인코넬 합금은 고니켈과 크롬의 합금으로 고온에서 내부식성이 뛰어난 특성을 가지고 있다. 본 연구에서는 인코넬 600 과 690 합금에 대해 실제 원전의 운전온도, 즉 $320^{\circ}C$가 프레팅 피로 거동에 미치는 영향에 대해 연구해보았다. 그 결과 $320^{\circ}C$에서의 단순 피로한도와 프레팅 피로한도가 상온에서의 단순 및 프레팅 피로한도에 비해 다소 저하하는 것을 알 수 있었다. 아울러 하중 반복회수와 마찰력의 변화 특성도 얻었다. 또한 파단면을 전자현미경으로 관찰하여 프레팅 피로기구도 검토해 보았다. 이와 같은 결과는 실제 운전온도에서 프레팅을 받는 증기발생기의 구조건전성 평가에 활용 가능할 것으로 생각된다.