Two-phase flow phenomena in broken recirculation line of BWR.

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概要

• 論文の詳細を見る

• When a primary recirculation line of BWR is ruptured, a primary recirculation pump may be subjected to very high velocity two-phase flow and its speed may be accelerated by this flow. It is important for safety evaluation to estimate the pump behavior during blowdown. There are two problems involved in analyzing this behavior. One problem concerns the pump characteristics under two-phase flow. The other involves the two-phase conditions at the pump inlet. If the rupture occurs at a suction side of the pump, choking is considered to occur at a broken jet pump nozzle. Then, a void fraction becomes larger downstream from the jet pump nozzle and volumetric flow through the pump will be very high. However, there is little experimental data available on two-phase flow downstream from a choking plane. Blowdown tests were performed using a simulated broken recirculation line and measured data were analyzed by TRAC-P1A. Analytical results agreed with measured data.

• 一般社団法人 日本原子力学会の論文

著者

• Narabayashi Tadashi

  Nuclear Engineering Lab. Toshiba Corp.

• NARABAYASHI Tadashi

  Nuclear Engineering Laboratory, Toshiba Corp.

• AMANO Osamu

  Tokyo Electric Power Co., Inc.

• ARAI Kenji

  NAIG Nuclear Research Laboratory, Nippon Atomic Industry Group Co., Ltd.

• KATO Masami

  NAIG Nuclear Research Laboratory, Nippon Atomic Industry Group Co., Ltd.

関連論文

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• Boiling water reactor loss-of-coolant tests with two bundle loop. Examination of conservativeness for licensing analysis models using large break test data.:Examination of Conservativeness for Licensing Analysis Models Using Large Break Test Data
• Estimation of centrifugal pump head in steam-water two-phase flow.

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