Development of BWR Regional Stability Experimental Facility SIRIUS-F, Which Simulates Thermalhydraulics-Neutronics Coupling in Reactor Core, And Stability Evaluation of ABWR

• FURUYA M.

収録刊行物

• Proc. 11th Int. Meeting on Nucl. Reactor Thermal-Hydraulics, 2005

  Proc. 11th Int. Meeting on Nucl. Reactor Thermal-Hydraulics, 2005 2005

詳細情報

• CRID: 1571698600532219520
• NII論文ID: 10021154441
• データソース種別:
  • CiNii Articles