Estimation of fuel channel inlet flow rate by noise analysis.

スポンサーリンク

概要

• 論文の詳細を見る

• Estimation of fuel channel inlet flow rate was performed, based upon the measurement of the void propagation time between two vertically placed neutron detectors in a BWR core. The procedure of estimation is as follows.<BR>First, the time of void propagation between two vertically placed neutron detectors is measured by the cross correlation method. Next, starting from the initial estimation of the coolant inlet flow rate for four fuel channels surrounding the detectors and the pressure drop between upper and lower plenums, the thermal-hydraulic calculation is performed iteratively to obtain the final value of coolant inlet flow rate in agreement with the measured void propagation time.<BR>The results show a good agreement with the fuel channel inlet flow value obtained by the theoretical calculation.

• 一般社団法人 日本原子力学会の論文

著者

• NAITO Norio

  Nippon Atomic Industry Group Co., Ltd.

• YAMAMOTO Fumiaki

  Toshiba Corp.

• TAKEUCHI Eiji

  Chubu Electric Power Co. Ltd.,

• TAKEUCHI Eiji

  Chubu Electric Power Co., Ltd.

• ANDO Yasumasa

  Nippon Atomic Industry Group Co., Ltd.

関連論文

• Development of BWR plant diagnosis systm using noise analysis.
• A Method of Reactor Physics Measurement with the Use of an Expanded System
• Estimation of fuel channel inlet flow rate by noise analysis.
• Identification of BWR Feedwater Control System using Autoregressive Integrated Model
• Identification of pressure control system dynamics in BWR plant by multivariate autoregressive modeling technique.

スポンサーリンク