Fracture Behavior of Irradiated Zircaloy-4 Cladding under Simulated LOCA Conditions

• Fumihisa Nagase

• Toyoshi Fuketa

書誌事項

タイトル別名

• Fracture Behavior of Irradiated Zircaloy 4 Cladding under Simulated LOCA Conditions
• Special Issue on Water Reactor Fuel Performance(2005 Water Reactor Fuel Performance Meeting)
• Special Issue on Water Reactor Fuel Performance 2005 Water Reactor Fuel Performance Meeting

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 43 (9), 1114-1119, 2006-09

  Tokyo : Atomic Energy Society of Japan

キーワード

• LWR type reactors
• high burnup
• Zircaloy
• hydriding
• oxidation
• quench
• threshold

詳細情報

• CRID: 1520009408849859072
• NII論文ID: 10017955893
• NII書誌ID: AA00703720
• ISSN: 00223131
• NDL書誌ID: 8061520
• Web Site: https://ndlsearch.ndl.go.jp/books/R000000004-I8061520
• 本文言語コード: en
• NDL 雑誌分類:
  • ZM35(科学技術--物理学)
• データソース種別:
  • NDL
  • CiNii Articles