An Improved One-and-a-Half Group BWR Core Simulator for a New-Generation Core Management System
スポンサーリンク
概要
- 論文の詳細を見る
An improved one-and-a-half group core simulator method for a next-generation BWR core management system is presented. In the improved method, intranodal spectral index (thermal to fast flux ratio) is expanded with analytic solutions to the diffusion equation, and the nodal power density and the interface net current are calculated, taking the intranodal flux shape into consideration. A unique method was developed for assembly heterogeneity correction. Thus eliminating the insufficiencies of the conventional one-and-a-half group method, we can have accurate power distributions as well as local peaking factors for cores having large spectral mismatch between fuel assemblies. The historical effects of spectral mismatch are also considered in both nodal power and local peaking calculations. Although reflectors are not solved explicitly, there is essentially no need for core dependent adjustable parameters, since boundary conditions are derived in the same manner as in the interior nodes. Calculation time for nodal solutions is comparable to that for the conventional method, and is less than 1/10 of a few-group nodal simulator. Verifications of the present method were made by comparing the results with those obtained by heterogeneous fine-mesh multi-group core depletion calculations, and the accuracy was shown to be fairly good.
- 一般社団法人 日本原子力学会の論文
著者
-
Iwamoto Tatsuya
Isogo Nuclear Engineering Center Toshiba Corporation
-
Yamamoto M
Isogo Nuclear Engineering Center Toshiba Corporation
-
Yamamoto Munenari
Isogo Nuclear Engineering Center Toshiba Corporation
関連論文
- Fission Product Model for BWR Analysis with Improved Accuracy in High Burnup
- Advanced Nodal Methods of the Few-Group BWR Core Simulator NEREUS
- Pin Power Reconstruction Methods of the Few-Group BWR Core Simulator NEREUS
- An Improved One-and-a-Half Group BWR Core Simulator for a New-Generation Core Management System