• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2006년도 춘계학술대회논문집
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• pp.250-253
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• 2006

The in-pile Section (IPS) is subjected to flow-induced vibration(FIV) due to the flow of the primary coolant and then the structural integrity. The in-pile Section (IPS) of 3-pin Fuel Test Loop(FTL) shall be installed in the vortical hole call IR1 of HANARO reactor core. In order to verify the velocity and displacement both the inside region of IPS at the annular region of IPS, the vibration was measured by varing the flow rate on both regions. The displacements of fuel assembly in the in-pile Section (IPS) were found to be lower than the values of allowable design criteria.

• 한국유체기계학회 논문집
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• 제12권5호
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• pp.7-12
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• 2009

A nuclear fuel test loop(after below, FTL) is installed in the IRI of an irradiation hole in HANARO for testing the neutron irradiation characteristics and thermo hydraulic characteristics of a fuel loaded in a light water power reactor or a heavy water power reactor. There is an in-pile section(IPS) and an out-pile section(OPS) in this test loop. When HANARO is operated normally, the fuel loaded into the IPS has a nuclear reaction heat generated by a neutron irradiation. To remove the generated heat and to maintain the operation conditions of the test fuel, a main cooling water system(MCWS) is installed in the OPS of the FTL. The MCWS is composed of a main cooler, a pressurizer, two circulation pumps, a main heater, an interconnection pipe line and instruments. The interconnection pipeline is a closed loop which is connected to an inlet and an outlet of the IPS respectively. The MCWS is under a cold function test during a start-up period. This paper describes the system flow network analysis results of the flow control of a main cooling water system in the HANARO fuel test loop. It was confirmed through the results that the flow was met the system design requirements.

• Nuclear Engineering and Technology
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• 제40권2호
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• pp.127-132
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• 2008

An experimental loop operating with water at supercritical conditions(25MPa, $600^{\circ}C$ in the test section) is designed for operation in the research reactor LVR-15 in UJV Rez, Czech Republic. The loop should serve as an experimental facility for corrosion tests of materials for in-core as well as out-of-core structures, for testing and optimization of suitable water chemistry for a future HPLWR and for studies of radiolysis of water at supercritical conditions, which remains the domain where very few experimental data are available. At present, final necessary calculations(thermalhydraulic, neutronic, strength) are being performed on the irradiation channel, which is the most challenging part of the loop. The concept of the primary and auxiliary circuits has been completed. The design of the loop shall be finished in the course of the year 2007 to start the construction, out-of-pile testing to verify proper functioning of all systems and as such to be ready for in-pile tests by the end of the HPLWR Phase 2 European project by the end of 2009.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2004년도 추계학술대회
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• pp.383-387
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• 2004

The Fuel Test Loop (FTL) consists of In-Pile Test Section (IPS) and Out-of-Pile System (OPS). The test condition in IPS such as pressure, temperature and quality of the main cooling water, can be controlled by the OPS. The FTL has been developed to be able to irradiate three pins to the core irradiation hole (IR1 hole) by considering for its utility and user's irradiation requirement. The IPS vessel assembly (IVA) consists of IPS head, outer pressure vessel, inner pressure vessel, inner assembly and test fuel carrier. The IVA is approximately 5.6 m long and fits within a 74 mm in diameter envelope over the full height of the chimney. Above the top of the chimney, the head of the IPS is enlarged to allow the closure flanges and pipe work connections. IVA was designed to test the CANDU and PWR nuclear fuel pin together. Specially, wished to minimize interference by nuclear fuel change in design and synthesize these items and shape design for IVA.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2007년도 춘계학술대회A
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• pp.291-295
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• 2007

FTL(Fuel Test Loop) is a facility that confirms performance of nuclear fuel at a similar irradiation condition with that of nuclear power plant. FTL consists of In-Pile Test Section (IPS) and Out-Pile System (OPS). FTL construction work began on August, 2006 and ended on March, 2007. During Construction, ensuring the worker's safety was the top priority and installation of the FTL without hampering the integrity of the HANARO was the next one. Task Force Team was organized to do a construction systematically and the communication between members of the task force team was done through the CoP(community of Practice) notice board provided by the Institute. The installation works were done successfully overcoming the difficulties such as on the limited space, on the radiation hazard inside the reactor pool, and finally on the shortening of the shut down period of the HANARO. Without a sweet of the workers of the participating company of HEC(Hyundae Engineering Co, Ltd), HDEC(HyunDai Engineering & Construction Co. Ltd), equipment manufacturer, and the task force team, it is not possible to install the FTL facility within the planned shutdown period. The Commissioning of the FTL is on due to check the function and the performance of the equipment and the overall system as well. The FTL shall start operation with high burn up test fuels in early 2008 if the commissioning and licensing progress on schedule.

• 헤리티지:역사와 과학
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• 제51권4호
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• pp.84-107
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• 2018

첨모직은 표면에 짧은 파일이 나타나는 것으로 조선시대 후기에는 첨모직 깔개를 지칭하는 용어로 채담이 사용되었으며, 20세기 초에는 융전과 단통, 양탄자 등으로 불리었다. 조선 말기 이후의 여러 문헌이나 신문기사, 그리고 각종 사진자료를 통해 첨모직 깔개가 왕실뿐만 아니라 일반인도 사용하였고 당시 국내에서 제작하였다는 것이 확인되었다. 본 연구에서는 조선 말기 이후의 첨모직 깔개 6점을 실물 조사하였는데 5점은 페르시아매듭의 컷파일이며 1점은 루프파일의 기법으로 제작되었다. 컷파일의 깔개는 크기가 가로 72~98 ${\times}$ 세로 150~156cm의 직사각형이며, 나비, 사슴, 호랑이, 그리고 십장생 등의 주 무늬를 중앙에 배치하고 卍자를 가장자리에 배치하였다. 컷파일의 소재는 지경사는 모두 면사이며 지위사는 3점은 면사, 1점은 모사, 그리고 1점은 면사와 비스코스레이온의 혼섬사이다. 지위사는 4점이 S꼬임의 실 여러 올을 합쳐 Z방향으로 합사한 실을 사용했다. 파일위사는 4~6가지의 색이 사용되었는데 홍색을 제외하고 모두 염색을 하지 않은 자연색 그대로의 모섬유가 사용되었다. 그리고 S나 Z꼬임의 모사를 2올 이상 합하여 반대방향으로 꼬임을 주었는데 굵기에 맞춰 올수를 합하였다. 깔개의 위아래 가장자리는 위사를 6올 이상 넣고 남은 지경사는 몇 올씩을 한데 묶어서 정리하였으며, 좌우 가장자리는 3올 이상의 면사를 가운데 놓고 수평으로 감아 마치 둥근 막대처럼 만들며, 가장자리에서 2~3번째 지경사를 징거서 튼튼하게 고정하였다. 루프파일은 경사방향으로 고리를 만든 경첨모직이며 지경사와 지위사는 면사, 파일경사는 모사로 추정된다. 소재의 성분 분석이 가능했던 깔개는 3점으로 파일위사는 판단이 불명한 것을 제외하고 염소와 비미종 양으로 판명되어 첨모직 깔개에 다양한 종류의 동물털이 사용되었을 가능성이 있다고 본다. 본 연구에서 조사한 6점의 깔개는 1800년대 말부터 1900년대 초에 제작되었다고 추정된다. 깔개의 정확한 제작지는 확인할 수 없었으나 당시 국내에서 첨모직 깔개를 제작하고 있다는 문헌기록과 깔개의 문양의 조형성을 고려한다면 우리나라에서 제작된 것으로 본다.

• 한국전산유체공학회:학술대회논문집
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• 한국전산유체공학회 2008년도 춘계학술대회논문집
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• pp.444-447
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• 2008

A nuclear fuel test loop (after below, FTL) is installed in IR1 of an irradiation hole in HANARO for testing neutron irradiation characteristics and thermo hydraulic characteristics of a fuel loaded in a light water power reactor (PWR) or a heavy water power reactor (CANDU). There is an in-pile section (IPS) and an out-pile section (OPS) in this test loop. When HANARO is normally operated, the fuel loaded in the IPS has a nuclear reaction heat generated by a neutron irradiation. To remove the generated heat and to maintain an operation condition of the test fuel, a main cooling water system (MCWS) is installed in the OPS of the FTL. The pump can not continuously suck a fluid and not pressurize the fluid during a cold function test. To verify the flow characteristics of the MCWS, a flow net work analysis has been conducted. When the higher elevation pipelines wholly filled with coolant, it was confirmed through the analysis results that the pump pressurized the coolant normally. And the analysis results described the system characteristics with operation temperature and pressure variation satisfactorily.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.1373-1374
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• 2004

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 요약집 춘계학술발표대회
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• pp.443.1-443.1
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• 2004

• 대한기계학회:학술대회논문집
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• 대한기계학회 2005년도 창립60주년 기념 추계 학술대회
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• pp.102.1-102.1
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• 2005