Safety Relief Valve Performance for Two-Phase Flow

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概要

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• The performance of main steam safety relief valve has been evaluated with respect only to the steam. In the present study, two-phase flow and subcooled water blow-out tests with model valves were performed in order to evaluate the valves characteristics and per-formance. From the test results, it was made clear that not only for the steam but also for the two-phase flow the measurement data were hardly affected by scaling and also that the reaction force of the fluid to the valve stem was hardly dependent upon the void fraction. Analytical study was performed using the two-phase flow model in the valve. The results of the analysis showed good agreement with the test data. It was shown from the test and analysis results that the reaction force of the two-phase flow and subcooled water to the valve stem was almost as much as that of the steam flow, and the integrity of the safety relief valve could be maintained.

著者

• Nagasaka Hideo

  Nuclear Engineering Laboratory Toshiba Corporation

• Narabayashi Tadashi

  Nuclear Engineering Lab. Toshiba Corp.

• OHTSUKI Yoshiteru

  The Tokyo Electric Power Co., Inc.

• NIWANO Masao

  Isogo Engineering Center, Toshiba Corp.

関連論文

• Safety Relief Valve Performance for Two-Phase Flow
• Analytical Study on Steam Jet Injector Pump to Next-Generation BWR
• Measurement of Void Distribution in Transient Flows
• Thermal Hydraulic Behavior in Upper Plenum during Refill-Reflood Phase of BWR LOCA, (II) : Characteristics of Residual Two-Phase Pool in Upper Plenum
• Two-phase flow phenomena in broken recirculation line of BWR.
• Centrifugal pump behavior in steady and transient two-phase flow.
• Estimation of centrifugal pump head in steam-water two-phase flow.

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