Critical Power Analysis with Mechanistic Models for Nuclear Fuel Bundles,(I) Models and Verifications for Boiling Water Reactor Application

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概要

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• The critical power analysis code for BWR fuel bundles, “CAPE-BWR”, was developed. The objective of the development is to predict dryout phenomena of liquid film on fuel rod surfaces without tuning any parameters even for fuel bundle design improvements. The major features of the code are modular structure with mechanistic models and parallel computation. The calculation methods were divided into three steps: subchannel, liquid film flow and spacer effect analyses. The code was validated by the rod bundle test analyses. The overall comparison of calculated critical power with 166 measured data points showed −0.3% average difference with the standard deviation of 6.3%. The spatial domain decomposition method was applied for parallel computation of the spacer effect analysis. The parallelization efficiency was about 80%. The calculated dryout location agreed well with the measured one at the full-scale 8×8 bundle test. The code could trace the tendencies of the critical power depending on power distribution, spacer geometry and fluid conditions within a practical range of difference. From the calculation, difference of the critical power due to the spacer geometry was clarified to be caused by the difference of droplet deposition characteristics onto the liquid film.

• 社団法人 日本原子力学会の論文
• 2002-01-25

著者

• NAITOH Masanori

  Nuclear Power Engineering Corporation

• OKAWA Tomio

  Department of Mechanophysics Engineering, Osaka University

• KATAOKA Isao

  Department of Mechanophysics Engineering, Osaka University

• Ikeda Takashi

  Advanced Simulation Systems Department, Nuclear Power Engineering Corporation

• NAITOH Masanori

  Advanced Simulation Systems Department, Nuclear Power Engineering Corporation

• Tomio Okawa

  Department Of Mechanical Engineering Osaka University

• Okawa Tomio

  Department Of Mechanophysics Engineering Osaka University

• Naitoh Masanori

  Advanced Simulation Systems Department Nuclear Power Engineering Corporation

• Naitoh Masanori

  Advanced Simulation Systems Department Nuclear Power Engineering Corporation Fujita Kanko

• Kataoka I

  Department Of Mechanical Engineering Osaka University

• Kataoka I

  Department Of Mechanophysics Engineering Osaka University

• Kataoka Isao

  Department Of Mechanical Engineering Graduate School Of Engineering Osaka University

• NISHIDA Koji

  Power & Industrial Systems R&D Laboratory, Hitachi, Ltd.

• Nishida Koji

  Power & Industrial Systems R&d Laboratory Hitachi Ltd.

• Okawa Tomio

  Department of Mechanical Engineering, Osaka University

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