高温工学試験研究炉の中間熱交換器の構造設計

• 国富 一彦

  日本原子力研究所 大洗研究所

• 竹田 武司

  日本原子力研究所 大洗研究所

• 篠崎 正幸

  日本原子力研究所 大洗研究所

• 大久保 実

  日本原子力研究所 大洗研究所

• 丸山 茂樹

  (株)東芝原子力事業部

• 小池上 一

  石川島播磨重工(株)原子力事業部

書誌事項

タイトル別名

• Structural Design for an Intermediate Heat Exchanger of the HTTR.

抄録

The Intermediate Heat Exchanger (IHX) of the High Temperature Engineering Test Reactor (HTTR) is a helium-helium type heat exchanger with the heat capacity of 10MW. The internal structures such as heat transfer tubes made of Hastelloy XR are used normally at about 930°C because the IHX can supply the secondary helium gas with the maximum temperature of 905°C transferred from the primary helium gas of 950°C. They compose the primary boundary and their creep strain and creep damage evaluated conservatively based on the elastic analysis cannot meet the required criteria with enough margin. The design method based on the complete creep analysis was used for the primary coolant boundary components. <BR>This report describes an evaluation procedure based on the creep analysis and its results. The results show that the creep strain and creep damage increased rapidly during a few initial cycles, however, increased far less after that. The results can meet the design limit for 10⁵h of the HTTR life time.

収録刊行物

• 日本原子力学会誌

  日本原子力学会誌 37 (4), 316-326, 1995

  一般社団法人 日本原子力学会

キーワード

• HTGR
• HTTR
• intermediate heat exchanger
• hot header
• creep
• creep strain
• creep damage
• creep analysis
• elastic analysjs
• design
• feasibility studies

詳細情報

• CRID: 1390282681527928576
• NII論文ID: 130003910092
• DOI: 10.3327/jaesj.37.316
• ISSN: 21865256
• ISSN: 00047120
• 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