http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
오비탈 TIG 용접시스템을 이용한 시험핵연료봉 봉단마개 용접기술 개발
정창용,홍진태,안성호,허성호,장서윤 한국기계기술학회 2015 한국기계기술학회지 Vol.17 No.4
To precisely assemble the fuel test rod, an orbital TIG welding system was designed and developed to accurately conduct orbital TIG welding for the nuclear fuel test rod. Using this system, a welding process needs to confirm the welding properties for orbital TIG welding. Therefore, preliminary weld tests were performed on the cladding tubes under various conditions, and the results show that the width and depth of HAZ of the cladding specimen welded using identical power during an orbital TIG welding cycle was continuously increased from a welded start-point to a welded end-point because of heat accumulation. The performance tests were conducted under the welding conditions considered through preliminary welding tests, and the properties of the specimens were conformed through surface and microstructure analyses.
중수로 핵연료 봉단마개의 저항업셋 용접을 위한 용접변수
이정원,박춘호,고진현,정성훈,정문규 대한용접접합학회 1989 대한용접·접합학회지 Vol.7 No.2
The present study was aimed at investigating the effect of welding parameters such as welding current, electrode force(or squeeze force) and parts cleaning on the sound weld, and establishing the most reliable weld conditions for HWP(Heavy Water Reactor) fuel end capping with the resistance upset butt welding. Major results obtained are as follows. 1. The amount of sound weld was increased with increasing weld current(5.0-11KA) because the activated diffusion with increasing heat generation played an important role in eliminating the porosity and weld line in the weld interface. 2. It was found that weld current was not significantly influenced by the electrode force although the increase of it caused a slight increase of weld current and upset deformation. 3. Acetone rinsing before drying for the Zircaloy-4 end cap cleaning produced the reliable sound weld because it would remove the remaining solvent and surface films, and provided the uniform contact between the end cap and the tube. 4. The optimum welding conditions for fuel end capping by a resistance upset hytt welding are obtained as follows. weld current: 10-11KA, electrode force: 62-90KPa parts cleaning: vapor degreasing.rarw.water, acetone rinsing.rarw.drying.
Nd:YAG LB 와 GTA 를 of용한 핵연료봉의 Zircaloy-4 봉단용접특성에 관한 연구
김수성,이정원,양명승,이영호 대한용접접합학회 1996 대한용접·접합학회지 Vol.14 No.6
This study is to compare the weldability of Zircaloy-4 end cap of nuclear fuel pin using by GTA and Nd :YAG LB. The welding parameters which affect bead width and penetration depth have been investigated. The effect of joint geometry of end cap for GTAW and LBW has been studied and optimum conditions of Zircaloy-4 endcap welding have been found. Microstructures and microhardness of GTA and LB welded zones have been also compared.
광섬유전송에 의한 Zircaloy-4 봉단마개밀봉의 Nd:YAG LBW의 최적조건에 관한 연구
김수성,김웅기,이영호 대한용접접합학회 1997 대한용접·접합학회지 Vol.15 No.6
This study is to investigate the optimum conditions of Nd:YAG laser beam welding for Zircaloy-4 end cap closure by optical fiber transmission. Laser welding parameters which affect the penetration depth and bead width were experimentally examined using the various beam radius by the beam quality analyzer, joint geometries of end cap and the laser parameters which mean pulse width, repetition rate and pulse energy. Also, an optimum welding speed and the effect of assistant gas with varying the flow rate of He were investigated. We found that the laser average power for the end cap welding will be 230W and rotation speed must not exceed 8 RPM, the best position of focus using optical fiber with 600.mu.m will be 2 to 3mm below the surface of the material.
Zr-4 피복관을 이용한 End Plug 용접특성 조사
김수성(Kim Soo-Sung),김형규(Kim Hyung-Kyu) 대한기계학회 2007 대한기계학회 춘추학술대회 Vol.2007 No.10
This study is to investigate the welding characteristics of Zr-4 end plug of fuel element in the cases of GTAW and LBW. The welding parameters which affect the bead width and the penetration depth have been also compared. The effect of joint geometry of end plugging for GTAW and LBW has been studied and optimum conditions of Zr-4 end-plug welding have been found. Futhermore, microstructures and micro-hardness of GTA and LB welded specimens have been also compared.
오비탈 TIG 용접시스템을 이용한 시험핵연료봉 봉단마개 용접기술 개발
정창용,홍진태,안성호,허성호,장서윤 한국기계기술학회 2015 한국기계기술학회지 Vol.17 No.4
To precisely assemble the fuel test rod, an orbital TIG welding system was designed and developed to accurately conduct orbital TIG welding for the nuclear fuel test rod. Using this system, a welding process needs to confirm the welding properties for orbital TIG welding. Therefore, preliminary weld tests were performed on the cladding tubes under various conditions, and the results show that the width and depth of HAZ of the cladding specimen welded using identical power during an orbital TIG welding cycle was continuously increased from a welded start-point to a welded end-point because of heat accumulation. The performance tests were conducted under the welding conditions considered through preliminary welding tests, and the properties of the specimens were conformed through surface and microstructure analyses.
내외부 이중튜브구조를 갖는 핵연료봉의 봉단마개 용접시험 평가
김수성(Kim Soo-Sung),김종헌(Kim Jong-Hun),김형규(Kim Hyung-Kyu) 대한기계학회 2008 대한기계학회 춘추학술대회 Vol.2008 No.11
An irradiation test of a nuclear fuel rod having external and internal tube structure was planned for a performance. To establish fabrication process satisfying the requirements of irradiation test, micro-TIG welding system for fuel rods was developed, and preliminary welding experiments for optimizing process conditions of fuel rod was performed. Fuel rods with 15.9㎜ diameter and 0.57㎜ wall thickness of cladding tubes and end caps have been used and optimum conditions of endcap welding have been selected. In this experiment, the qualification test was performed by tensile tests, helium leak inspections, and metallography examinations to qualify the endcap welding procedure. The soundness of the welds quality of a dual cooled fuel rods has been confirmed by mechanical tests and microstructural examinations.
김수성(Kim Soo-sung),김형규(Kim Hyung-kyu) 대한기계학회 2010 대한기계학회 춘추학술대회 Vol.2010 No.11
The optimization of the GTAW parameters was carried out for the dual fuel rod fabrication by using a micro-GTA welder. STS 316 end-plugs and cladding tubes were used for the dual fuel rod welding. The four welding parameters were selected through preliminary experiments and their effects on the penetration depth were analyzed statistically. The design of experiments were used and carried out by using the Taguchi experimental method with a L?2? orthogonal array.
김수성(Kim Soo-Sung),김종헌(Kim Jong-Hun),김형규(Kim Hyung-Kyu) 대한기계학회 2009 대한기계학회 춘추학술대회 Vol.2009 No.5
An irradiation test of a nuclear fuel rod having a external and an internal tube structure was planned for a performance. To establish fabrication process satisfying the requirements of irradiation test, micro-GTA welding system for fuel rods was developed, and preliminary welding experiments for optimizing process conditions of fuel rod was performed. Fuel rods with 15.9㎜ diameter and 0.57㎜ wall thickness of cladding tubes and end caps have been used and optimum conditions of end cap welding have been selected. In this experiment, preliminary qualification test was performed by tensile tests, helium leak inspections, and metallography examinations to qualify the end cap welding procedure. The soundness of the welds quality of a dual cooled fuel rods has been confirmed by mechanical tests and micro-structure examinations.