B205 A STUDY ON TWO-PHASE NATURAL CONVECTION USING THE BETHSY EXPERIMENT AND THE THERMAL-HYDRAULIC CODE MARS 1.4(Nuclear power-2)

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概要

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• A thermal-hydraulic analysis was conducted on the two-phase natural convection of the BETHSY facility. The test represents the cooling states of the primary cooling system under two-phase natural convection for the given conditions. Based on MARS code calculations, the major thermal-hydraulic behaviors during the two-phase natural convection are evaluated, and the differences between the experimental and calculated results are identified. The calculated results show generally good agreement with the experimental data. However the prediction of the peak flow in the primary system and the pressure difference between the outlet and inlet sides of the SG u-tubes are not appropriate for the first half period. The liquid distribution in the u-tubes and the downcomer mass flow are sensitive to the interfacial drag force. It is necessary to extensively study the interfacial drag in MARS code for the each flow regime under two-phase natural convection.

• 一般社団法人日本機械学会の論文
• 2000-10-01

著者

• Chang Moon

  Korea Atomic Energy Research Institute

• SIM Suk

  Korea Atomic Energy Research Institute

• Sim Suk

  Environment & Energy Technology(en2t)

• Chung Young

  Korea Atomic Energy Research Institute(kaeri)

• Bae Kyoo

  Korea Atomic Energy Research Institute

• Bae Kyoo

  Korea Atomic Energy Research Institute(kaeri)

関連論文

• Development and Assessment of the COBRA/RELAP5 Code
• B205 A STUDY ON TWO-PHASE NATURAL CONVECTION USING THE BETHSY EXPERIMENT AND THE THERMAL-HYDRAULIC CODE MARS 1.4(Nuclear power-2)
• B204 EVALUATION OF THE KNGR DIRECT VESSEL SAFETY INJECTION SYSTEM FOR A LARGE BREAK LOCA USING MARS 1.4(Nuclear power-2)
• An Application of a Variable Overpower Trip Function with Multiple Ceilings into an Advanced Integral Reactor
• Development of a Computer Code,ONCESG,for the Thermal-Hydraulic Design of a Once-Through Steam Generator

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