Critical Power Evaluation with Consideration of Differences in Droplet Behavior due to Spacer Shape Influence.

• KANAZAWA Toru

  Energy Research Laboratory, Hitachi Ltd.

• NISHIDA Koji

  Energy Research Laboratory, Hitachi Ltd.

• NAGAYOSHI Takuji

  Energy Research Laboratory, Hitachi Ltd.

• KAWASAKI Terufumi

  Energy Research Laboratory, Hitachi Ltd.

• YOKOMIZO Osamu

  Energy Research Laboratory, Hitachi Ltd.

抄録

An evaluation method for droplet deposition coefficients, corresponding to spacer shapes, was developed in order to predict nuclear fuel bundle critical power. The method is based on a three-dimensional numerical analysis of dispersed flow around the spacer. The analysis showed that coolant droplet deposition characteristics onto fuel rods differed between grid type and ferrule type spacers, and also between fuel rods due to flow tabs on the upper end of the spacer band. The droplet deposition coefficient was modeled from the analysis results and adopted into a critical power prediction code based on subchannel analysis. Comparisons between critical powers calculated by the subchannel analysis code and those measured with full-scale test assemblies showed good agreement and improved prediction accuracy of the code.

収録刊行物

• Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌）

  Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌） 32 (4), 301-312, 1995

  一般社団法人 日本原子力学会

キーワード

• fuel bundles
• fuel element clusters
• critical power
• dryout
• spacers
• droplets
• deposition
• subchannel analysis
• spacer model
• droplet deposition coefficient
• coolants

詳細情報

• CRID: 1390282679072254464
• NII論文ID: 10002072352
• NII書誌ID: AA00703720
• DOI: 10.3327/jnst.32.301
• COI: 1:CAS:528:DyaK2MXltFaktbc%3D
• ISSN: 18811248
• ISSN: 00223131
• 本文言語コード: en
• データソース種別:
  • JaLC
  • Crossref
  • CiNii Articles
• 抄録ライセンスフラグ: 使用不可