박사

KSTAR PFC용 평판형 텅스텐과 CuCrZr의 브레이징 접합 및 열적 안정성에 관한 연구

김경민 2017년
논문상세정보
    • 저자 김경민
    • 기타서명 (A) study on thermal stability and brazing bonding between flat type tungsten and CuCrZr for KSTAR PFC
    • 형태사항 ix, 131p.: 26 cm
    • 일반주기 지도교수: 유성연, 지도교수: 이제묘, 충남대학교 논문은 저작권에 의해 보호받습니다, 참고문헌 : p. 121-126
    • 학위논문사항 2017. 2, 忠南大學校 大學院, 학위논문(박사)-, 기계·기계설계·메카트로닉스공학과 첨단에너지시스템 전공 전공
    • DDC 22, 621.8
    • 발행지 대전
    • 언어 kor
    • 출판년 2017
    • 발행사항 忠南大學校 大學院
    유사주제 논문( 529)
' KSTAR PFC용 평판형 텅스텐과 CuCrZr의 브레이징 접합 및 열적 안정성에 관한 연구' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
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동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
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' KSTAR PFC용 평판형 텅스텐과 CuCrZr의 브레이징 접합 및 열적 안정성에 관한 연구' 의 참고문헌

  • Z. Zhou, S. Song, W. Yao, G. Pintsuk, J. Linke, S. Guo, C. Ge, “Fabrication of thick W coatings by atmospheric plasma spraying and their transient high heat loading performance”, Fusion Engineering and Design, Vol. 85 (2010) 1720-1723.
  • Z. Zhou, D. Yao, L. Cao, C. Liang, “The design and R&D work of EAST tungsten divertor”, IEEE 25th Symposium on Fusion Engineering, San Francisco, California (2013) 1-4.
  • Y. S. Bae, “Status and plan of KSTAR heating systems for steady state plasma achievement”, Proceedings of A3 foresight program seminar (2013) 34-37.
  • Y. Patil, S. S. Khirwadkar, S. M. Belsare, R. Swamy, M. S. Khan, S. Tripathi, K. Bhope, et al., “Performance of straight tungsten monoblock test mockups using new high heat flux test facility at IPR”, Fusion Engineering and Design, Vol. 95 (2015) 84-90.
  • Y. Patil, S. S. Khirwadkar, D. Krishnan, A. Patel, S. Tripathi, K. P. Singh, S. M. Belsare, “High heat flux performance of brazed tungsten macrobrush test mockup for divertor”, Journal of Nuclear Materials, Vol. 437 (2013) 326-331.
  • Y. I. Jung, J. Y. Park, B. K. Choi, Y. H. Jeong, D. W. Lee, S. Y. Cho, “Joining methods of Be/FMS and W/FMS for the ITER TBM first wall”, Fusion Engineering and Design, Vol. 86 (2011) 2390-2393.
  • X. Liu, F. Zhang, S. Tao, Y. Cao, Z. Xu, Y. Liu, N. Noda, “Research and development of plasma sprayed tungsten coating on graphite and copper substrates”, Journal of Nuclear Materials, Vol. 363 (2007) 1299-1303.
  • W. Shen, Q. Li, K. Chang, Z. Zhou, C. Ge, “Manufacturing and testing W/Cu functionally graded material mockups for plasma facing components”, Journal of Nuclear Materials, Vol. 367 (2007) 1449-1452.
  • V. Philipps, “Tungsten as material for plasma facing components in fusion devices”, Journal of Nuclear Materials, Vol. 415 (2011) S2-S9.
  • T. Ontaku, Y. J. Kim, “Principle and basics of diffusion bonding”, Journal of the Korean Welding Society, Vol. 6, No. 1 (1988) 2-10.
  • S. Suzuki, K. Ezato, Y. Seki, K. Mohri, K. Yokoyama, M. Enoeda, “Development of the plasma facing components in Japan for ITER”, Fusion Engineering and Design, Vol. 87 (2012) 845-852.
  • S. Saito, K. Fukaya, S. Ishiyama, K. Sato, “Mechanical properties of HIP bonded W and Cu alloys joint for plasma facing components”, Journal of Nuclear Materials, Vol. 307 (2002) 1542-1546.
  • S. S. Khirwadkar, K. P. Singh, Y. Patil, M. S. Khan, J. J. Buch, A. Patel, et al., “Fabrication and characterization of tungsten and graphite based PFC for divertor target elements of ITER like tokamak application”, Fusion Engineering and Design, Vol. 86 (2011) 1736-1740.
  • S. K. Kim, H. G. Jin, K. I. Shin, et al., “Manufacturing and examination for ITER blanket first wall small scale mockups with KoHLT-EB in Korea”, IEEE Transaction on Plasma Science, Vol. 42, No. 5 (2014) 1438-1442.
  • R. N. Giniyatulin, V. L. Komarov, E. G. Kuzmin, A. N. Makhankov, I. V. Mazul, N. A. Yablokov, A. N. Zhuk, “Optimization of armour geometry and bonding techniques for tungsten armoured high heat flux components”, Fusion Engineering and Design, Vol. 61 (2002) 185-190.
  • R. Matera, G. Federici, ITER joint central team, “Design requirements for plasma facing materials in ITER”, Journal of Nuclear Materials, Vol. 233 (1996) 17-25.
  • R. A. Pitts, S. Carpentier, F. Escourbiac, T. Hirai, V. Komarov, S. Lisgo, et al., “A full tungsten divertor for ITER: Physics issues and design status”, Journal of Nuclear Materials, Vol. 438 (2013) S48-S56.
  • Q. Li, S. Qin, W. Wang, P. Qi, S. Roccella, E. Visca, et al., “Manufacturing and testing of W/Cu monoblock small scale mockup for EAST by HIP and HRP technologies”, Fusion Engineering and Design, Vol. 88 (2013) 1808-1812.
  • P. Norajitra, S. Abdel-Khalik, L. Giancarli, T. Ihli, G. Janeschitz, S. Malang, et al., “Divertor conceptual designs for a fusion power plant”, Fusion Engineering and Design, Vol. 83 (2008) 893-902.
  • N. Y. Chung, “Technical specification for manufacturing and assembly of the 2nd cooling water utility for KSTAR PFC”, National Fusion Research Institute, Vol. 1 (2016) 21-46.
  • N. Litunovsky, E. Alekseenko, V. Kuznetsov, D. Lyanzberg, A. Makhankov, R. Rulev, “Repair of manufacturing defects in the armor of plasma facing units of the ITER divertor dome”, Fusion Engineering and Design, Vol. 88 (2013) 1739-1743.
  • N. Litunovsky, E. Alekseenko, A. Makhankov, I. Mazul, “Development of the armoring technique for ITER divertor dome”, Fusion Engineering and Design, Vol. 86 (2011) 1749-1752.
  • N. Holtkamp, “The status of the ITER design”, Fusion Engineering & Design, Vol. 84 (2009) 98-105.
  • M. Merola, G. Vieider, M. Bet, I. Vastra, L. Briottet, P. Chappuis, et al., “European achievements for ITER high heat flux components”, Fusion Engineering and Design, Vol. 56-57 (2001) 173-178.
  • M. Bisio, V. Branca, M. Di Marco, A. Federici, M. Grattarola, G. Gualco, et al., “Manufacturing and testing in reactor relevant conditions of brazed plasma facing components of the ITER divertor”, Fusion Engineering and Design, Vol. 75 (2005) 277-283.
  • Korea Basic Science Institute, “Engineering Design on the KSTAR PFC”, Engineering Design Report, Vol. 1 (2003) 1-51.
  • K. M. Kim, H. T. Kim, J. H. Song, H. K. Kim, S. H. Park, S. H. Hong, et al., “Manufacturing and high heat flux testing of tungsten brazed mockups for KSTAR divertor”, IEEE 26th Symposium on Fusion Engineering, Austin, Texas (2015) 1-4.
  • K. M. Kim, E. N. Bang, H. T. Kim H. K. Kim, K. S. Lee, H. L. Yang, et al., “The KSTAR plasma facing components for 2010 operation”, Fusion Engineering & Design, Vol. 86, issue 9-11 (2011) 1693-1696.
  • K. Ezato, S. Suzuki, Y. Seki, H. Nishi, K. Mohri, M. Enoeda, “R&D activities on manufacturing plasma facing unit for prototype of ITER divertor outer target in JADA”, Fusion Engineering and Design, Vol. 87 (2012) 1177-1180.
  • J. S. Lee, J. Y. Park, B. K. Choi, B. G. Hong, Y. H. Jeong, “Effects of cooling rate and aging treatment on the mechanical properties of CuCrZr alloys for ITER first wall” Journal of the Korean Society for Heat Treatment, Vol. 20, No. 3 (2007) 133-139.
  • J. S. Bak, C. H. Choi, H. L. Yang, J. W. Sa, H. K. Kim, B. C. Kim, et al., “Key Feature & Engineering Progress of the KSTAR Tokamak”, IEEE transactions on Plasma Science, Vol. 32, No. 2 (2004) 757-763.
  • J. Linke, “Plasma facing materials and components for future fusion devices”, Physica Scripta, T123 (2006) 45-53.
  • J. H. Song, K. M. Kim, K. Im, S. H. Hong, H. T. Kim, H. K. Kim, et al., “Conceptual design of tungsten monoblock components for KSTAR divertor”, IEEE Transactions on Plasma Science, Vol. 44, No. 9 (2016) 1529-1533.
  • J. Dietz and ITER joint central team, “The ITER fusion experiment”, Vacuum, Vol. 47, No. 6/8 (1996) 911-918.
  • ITER Organization, “ITER material properties handbook”, No. G 74 MA9 (2007) 148-152.
  • H. Li, J. L. Chen, J. G. Li, X. J. Sun, “High heat load tests on W-Cu mockups and evaluation of their application to EAST device”, Fusion Engineering and Design, Vol. 84 (2009) 1-4.
  • H. L. Yang, “Upgrade of the KSTAR device for the advanced plasma experiments”, Divertor Workshop, Daejeon, Apr. 3rd, 2014, unpublished.
  • H. L. Yang, J. S. Bak, B. C. Kim, C. H. Choi, W. C. Kim, N. I. Her, and KSTAR team, “Construction, Assembly and Commissioning of KSTAR main structures”, Nuclear Engineering & Technology, Vol. 40, No. 6 (2008) 439-450.
  • G. S. Lee, J. Kim, S. M. Hwang, C. S. Chang, H. Y. Chang, M. H. Cho, et al., “The Design of the KSTAR Tokamak”, Fusion Engineering & Design, Vol. 46 (1999) 405-411.
  • E. Visca, E. Cacciotti, A. Komarov, S. Libera, N. Litunovsky, A. Makhankov, et al., “Manufacturing, testing and post-test examination of ITER divertor vertical target W small scale mockups”, Fusion Engineering and Design, Vol. 86 (2011) 1591-1594.
  • C. Y. Kang, “Design of brazing joints: design of joint clearance”, Journal of Korean Welding Society, Vol. 18, No. 3 (2000) 1225-1229.
  • C. D. Lee, S. J. Na, “A study on the vacuum brazing carbon steels to a stainless steel”, Journal of Korean Society of Mechanical Engineers, Vol. 12, No. 5 (1988) 1083-1091.
  • A. V. Bui, N. T. Dinh, R. R. Nourgaliev, B. J. Williams, “Statistical modeling support for calibration of multiphysics model of subcooled boiling flows”, International conference on Mathematics and Computational methods applied to Nuclear Science & Engineering, Sun Valley, Idaho (2013) 1-16.