• 비파괴검사학회지
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• 제34권5호
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• pp.384-389
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• 2014

본 논문에서는 국내 원자력발전소 초음파검사자 기량검증시험 결과를 검토하였다. 원자력발전소 안전관련 설비에 대한 초음파검사 기량검증 요건은 ASME B&PV Code Section XI 1989 겨울 부록에서 최초로 언급되었다. 한국수력원자력(주)은 ASME Code Section XI, Appendix VIII의 요건 적용을 위해 국내 원자력발전소에 적합한 한국형 초음파검사 기량검증(KPD) 시스템을 개발, 규제기관의 승인을 받아 2004년 7월부터 운영하고 있다. 본 논문에서는 2004년부터 2013년까지 수행한 초음파검사자 기량검증시험 결과의 검토 내용으로 초음파검사 결함 검출 향상 및 기량훈련시스템 연구 개발에 도움을 줄 것으로 기대한다.

• 비파괴검사학회지
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• 제25권3호
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• pp.228-232
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• 2005

The Korea Electric Power Research Institute (KEPRI) has developed performance demonstration programs for non-destructive testing personnel who analyze ECT(eddy current testing) data for steam generator tubing since 2001 The purpose of these performance demonstration programs is to ensure a uniform knowledge and skill level of data analysts and contribute to safe operation of nuclear power plants. Many changes have occurred in non-destructive testing of steam generator tubing such as inspection scope, plugging criteria and qualification requirements. According to the Notice 2004-13 revised by the Ministry of Science and Technology (MOST), the analyst for steam generator tubing shall be qualified as the qualified data analyst (QDA), and the site specific performance demonstration (SSPD) program shall be implemented. KEPRI developed these performance demonstration programs and they are being successfully implemented. The analyst's performance is expected to be improved by the implementation of these programs.

• 한국압력기기공학회 논문집
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• 제10권1호
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• pp.44-50
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• 2014

There were many flaw issues of reactor vessel head penetration in USA fleets. USNRC issued 10CFR50.55a to implement reactor vessel head penetration ultrasonic examination performance demonstration(PD) in US for enhancement of inspection reliability. After September 2009, all US utilities inspected their RVHP with PD qualified system. Korea Hydro and Nuclear Power Company(KHNP) have developed reactor vessel head penetration performance demonstration system for ultrasonic test to apply for pressurized light-water reactor power plants in accordance with 10CFR50.55a since September 2011. RVHP configuration surveying and analysis, code requirement analysis, and performance demonstration specimen design were performed up to this day. Fingerprinting of manufactured specimen, development of test data management program, development of operation procedure, input of flawed data, and development of final report will be performed for the next step. This paper describes the development status of the performance demonstration system for reactor vessel head penetration ultrasonic examination in Korea.

• 한국콘텐츠학회논문지
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• 제11권12호
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• pp.1-11
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• 2011

어플리케이션의 시연은 일련의 상호작용을 포함하기 때문에 많은 시간이 소요된다. 어플리케이션을 시연해야 한다면 통상적으로 발표 세션과 별도로 시연 세션을 진행한다. 하지만, 모바일 단말기를 조작하여 무선으로 어플리케이션을 시연한다면 발표자가 직접 시연을 주도적으로 진행함으로써 전달하고자 하는 메시지를 효과적으로 전달할 수 있을 것이다. 이러한 시연 방법은 기존 모바일 단말기의 성능과 화면 크기의 제약 때문에 구현이 불가능하였다. 우수한 성능과 다양한 기능을 갖춘 스마트폰의 등장으로 스트림 동영상을 실시간으로 그리고 상대적으로 큰 모바일 단말기 화면에서 재생할 수 있고, 또한 시연자가 모바일 단말기 화면의 어플리케이션 영상을 보면서 어플리케이션을 직접 제어할 수 있기 때문에 새로운 시연 방법의 구현이 가능해졌다. 본 논문은 스마트폰을 활용한 모바일 기반 시연 시스템인 '스마트 데모(Smart Demo)'의 설계와 구현에 대해 기술하고자 한다.

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4474-4480
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• 2022

Deep geological disposal using a multibarrier system is a promising solution for treating high-level radioactive (HLRW) waste. The HLRW canister represents the first barrier for the migration of radionuclides into the biosphere, therefore, the corrosion behavior of canister materials is of significance. In this study, the electrochemical behaviors of SS316L, Ti-Gr.2, Alloy 22, and Cu in naturally aerated KAERI underground research tunnel (KURT) groundwater solutions were examined. The corrosion potential, current, and impedance spectra of the test materials were recorded using electrochemical methods. According to polarization and impedance measurements, Cu exhibits relatively higher corrosion rates and a lower corrosion resistance ability than those exhibited by the other materials in the given groundwater condition. In the anodic dissolution tests, SS316L exposed to the groundwater solution exhibited the most uniform corrosion, as indicated by its surface roughness. This phenomenon could be attributed to the extremely low concentration of chloride ions in KURT groundwater.

• 한국기계가공학회지
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• 제20권2호
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• pp.107-119
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• 2021

The cross-flow turbine is one of the most famous and widely used hydraulic power systems for a long time. The cross-flow turbine is especially popular in many countries and remote regions where off-grided because of its many benefits such as low cost, high efficiency at low head, simple structure, and easy maintenance. However, most modern turbines, including the cross-flow turbine, are unsuitable for the ultra-low head situation, known as less than 3m water head or zero head with over 0.5m/s flow velocity. In this study, we demonstrated a 20kW class inverted-type cross-flow turbine's performance. First, we reevaluated our previous studies and introduced how to design the inverted-type cross-flow turbine. Secondly, we fabricated the 20kW class inverted-type cross-flow turbine for the performance test. And then, we designed a testbed and installed the turbine system in the demonstration facility. In the end, we compare the demonstration with its previous CFD results. The comparing result shows that both CFD and real model fitted on guide vane angle at 10 degrees. At the demonstration, we achieved 42% turbine efficiency at runner speed 125 RPM.

• 연구논문집
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• 통권32호
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• pp.55-64
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• 2002

Performance demonstration with real flawed specimens has been strongly required for nondestructive evaluation of safety class components in nuclear power plant. Specimen has been designed to produce mechanical fatigue flaw with tension stress and fatigue flaw has been produced to control stress and cycle, for suitable roughness. Notch condition is considered for control of fracture mode. After seal welding for fracture surface, final welding was performed to complete flaw specimen with GTAW(Gas Tungsten Arc welding) and FCAW(Flux Cored Arc Welding). It was demonstrated flaw size of flawed specimen by radiographic. testing and ultrasonic testing.

• 한국태양에너지학회 논문집
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• 제26권4호
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• pp.119-126
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• 2006

This study describes thermal performance of heating and cooling demonstration system using ETSC(Evacuated tubular solar collector) installed at Seo-gu art center of Kwangju. For demonstration study, a reading room with about $350m^2$ was heated and cooled using that system. The demonstration system was consisted of ETSCs, storage tank, hot water supply tank, subsidiary boiler, and subsidiary tank. From January to March in 2006, demonstration test were performed with 4 control mode to find the optimum control condition for solar thermal system. After experiments and analysis, this study found that solar thermal system of control mode IV was corresponded to 78% for the hot water supply and 49% for space heating.

• 한국추진공학회:학술대회논문집
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• 한국추진공학회 2009년도 제33회 추계학술대회논문집
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• pp.15-18
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• 2009

우주발사체 개발을 위한 75톤급 액체로켓엔진 개발에 앞서 선행개발을 통해 습득한 30톤급 액체로켓 엔진 기술을 토대로 75톤급 액체로켓엔진 연소기 기술 검증에 착수하였다. 이를 위하여 국내 연소시험 설비 여건을 고려한 기술검증 계획을 수립하고 기술검증시제를 제작하여 제한된 조건에서 성능평가시험을 수행하였다. 본 논문은 75톤급 액체로켓 연소기 기술검증을 위한 계획과 현황에 대하여 소개한다.

• 대한설비공학회:학술대회논문집
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• 대한설비공학회 2006년도 하계학술발표대회 논문집
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• pp.832-837
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• 2006

This study describes thermal performance of heating and cooling demonstration system using ETSC(Evacuated tubular solar collector) installed at Seo-gu art center of Kwangju. For demonstration study, a reading room with about $331m^2$ was heated and cooled using that system. The demonstration system was consisted of ETSCs, storage tank, hot water supply tank, subsidiary boiler, and subsidiary tank. From January to March in 2006, demonstration test were performed with 4 control mode to find the optimum control condition for solar thermal system. After experiments and analysis, this study found that solar thermal system of control mode IV was corresponded to 78% for the hot water supply and 49% for space heating.