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[ASME 17th International Conference on Nuclear Engineering - Brussels, Belgium (July 12–16, 2009)] Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance - The Hot Function Flow Characteristics of a Main Cooling Water System for the Nuclear Fuel Test Loop Installed in HANARO

[ASME 17th International Conference on Nuclear Engineering - Brussels, Belgium (July 12–16, 2009)] Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance - The Hot Function Flow Characteristics of a Main Cooling Water System for the Nuclear Fuel Test Loop Installed in HANARO

Park, Young-Chul; Lee, Young-Seob; Chi, Dae-Young
  • 作者Park, Young-Chul; Lee, Young-Seob; Chi, Dae-Young
  • 文件大小565.60KB
  • 发表时间2009
  • DOI10.1115/ICONE17-75282
  • 页码269-275
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