B203 改良TRAC-BF1コードによる直管型蒸気発生器の流動安定性評価手法の開発(OS8 熱流動),動力エネルギーシステム部門20周年,次の20年への新展開)

• 中塚 亨

  原子力機構

• 劉 維

  原子力機構

• 吉田 啓之

  原子力機構

• 高瀬 和之

  原子力機構

書誌事項

タイトル別名

• B203 Development of evaluation method of thermal-hydraulic stability of once-through steam generator by enhanced TRAC-BF1

抄録

To assess the stability of once-through steam generators in FBR, Japan Atomic Energy Agency has been developing a prediction method for thermal-hydraulic instability based on system analysis code TRAC-BF1. In the present paper, to simulate the primary coolant in steam generators, thermal property of sodium was incorporated to the code and the VESSEL component was improved to handle two different fluids of primary sodium and secondary water. These added functions were assessed with a simplified steam generator model calculation by altering primary coolant fluid as water and sodium. It was confirmed that heat transfer at steam generators was properly evaluated for the case that primary coolant is sodium as well as water.

収録刊行物

• 動力・エネルギー技術の最前線講演論文集 : シンポジウム

  動力・エネルギー技術の最前線講演論文集 : シンポジウム 2010.15 (0), 279-280, 2010

  一般社団法人 日本機械学会

キーワード

• Instability
• TRAC-BF1
• Parallel Channels
• Once-through Steam Generator
• Sodium

詳細情報

• CRID: 1390001205886975872
• NII論文ID: 110008739989
• DOI: 10.1299/jsmepes.2010.15.279
• ISSN: 24242950
• Web Site: https://www.jstage.jst.go.jp/article/jsmepes/2010.15/0/2010.15_279/_pdf
• 本文言語コード: ja
• 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