Development an Verification of and Efficient Spatial Neutron Kinetics Method for Reactivity-Initiated Event Analyses

スポンサーリンク

概要

• 論文の詳細を見る

• A space/time nodal diffusion code based on the nodal expansion method (NEM), EPISODE, was developed in order to evaluate transient neutron behavior in light water reactor cores. The present code employs the improved quasi-static (IQS) method for spatial neutron kinetics, and neutron flux distribution is numerically obtained by solving the neutron diffusion equation with the nonlinear iteration scheme to achieve fast computation. A predictor-corrector (PC) method developed in the present study enabled to apply a coarse time mesh to the transient spatial neutron calculation than that applicable in the conventional IQS model, which improved computational efficiency further. Its computational advantage was demonstrated by applying to the numerical benchmark problems that simulate reactivity-initiated events, showing reduction of computational times up to a factor of three than the conventional IQS. The thermohydraulics model was also incorporated in EPISODE, and the capability of realistic reactivity event analyses was verified using the SPERT-III/E-Core experimental data.

• 社団法人 日本原子力学会の論文
• 2001-07-25

著者

• IKEDA Hideaki

  In-core Fuel Management Department, Tepco Systems Corp.

• TAKEDA Toshikazu

  Nuclear Enginering Department, Osaka University

• Takeda Toshikazu

  Nuclear Engineering Department Osaka University

• Ikeda Hideaki

  In-core Fuel Management Department Toden Software Inc.

関連論文

• Effect of Moderator Density Distribution of Annular Flow on Fuel Assembly Neutronic Characteristics in Boiling Water Reactor Cores
• Nonlinear Behavior under Regional Neutron Flux Oscillations in BWR Cores
• Spatial-harmonic Neutron Spectrum Effect on Frequency-domain Modal Analysis of Regional Stability in BWR
• Development an Verification of and Efficient Spatial Neutron Kinetics Method for Reactivity-Initiated Event Analyses
• Effective Convergence of Fission Source Distribution in Monte Carlo Simulation
• Effect of Radial Void Distribution within Fuel Assembly on Assembly Neutronic Characteristics

スポンサーリンク