Prediction of transient boiling transition in BWR fuel rod bundles by subchannel analysis program MENUETT.

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概要

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• Transient CHF (critical heat flux) tests of a 4 × 4 rod bundle were analyzed by the subchannel analysis program MENUETT. MENUETT is based on a non-equilibrium, five equation, two-phase flow model and is available both for steady state and transient analyses. Turbulent mixing and void drift effects are taken into account to calculate cross flows in fuel rod bundles. The tendency of calculated subchannel mass fluxes and qualities agreed with experimental data. By using a critical quality correlation obtained from steady state CHF data, the position of the earliest boiling transition could be predicted regardless of non-uniform axial heat flux distributions. This transition occurrence time was predicted within a difference of 0.10.3 s from the experimental time. MENUETT applicability was confirmed for transient calculations predicting thermal-hydraulic behavior in bundles.

• 一般社団法人 日本原子力学会の論文

著者

• ISHII Yoshihiko

  Energy Research Laboratory, Hitachi Ltd.

• BESSHO Yasunori

  Energy Research Laboratory, Hitachi Ltd.

• UCHIKAWA Sadao

  Energy Research Laboratory, Hitachi Ltd.

関連論文

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• A new method of startup planning for boiling water reactors.
• Prediction of transient boiling transition in BWR fuel rod bundles by subchannel analysis program MENUETT.

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