Reactions between U - Pu - Zr Alloys and Fe at 923 K
スポンサーリンク
概要
- 論文の詳細を見る
In metallic U–Pu–Zr fuel, metallurgical reactions occur between the fuel slug and the cladding, and a phase of which the melting point is relatively low is formed in the reaction zone. If a liquid phase is formed, it can degrade cladding integrity. The potential for liquid phase formation near the cladding, therefore, should be excluded during normal reactor operation. In order to clarify the mechanism of liquefaction, the authors have conducted diffusion experiments at 923 K using two couples: U–13 at%Pu–22 at%Zr/Fe and U–22 at%Pu–22 at%Zr/Fe, and examined the influence of the Pu content in the fuel alloy on the phases formed in the reaction zones. The liquid phase has been observed in the U–22 at%Pu–22 at%Zr/Fe couple. An assessment of the diffusion paths for these couples has indicated that the Pu content in the (U, Pu)6Fe-type phase in the reaction zone is a crucial factor in determining the conditions that lead to liquefaction. The Pu content in the (U, Pu)6Fe-type phase increases with that in the initial U–Pu–Zr alloy. The fuel design specifications to exclude the potential for liquefaction will be clarified by further examination of the Pu content in the (U, Pu)6Fe-type phase for various U–Pu–Zr/Fe couples annealed at different temperatures.
- 社団法人 日本原子力学会の論文
- 2000-03-25
著者
-
Kurata Masaki
Central Research Institute of Electric Power Industry
-
YOKOO Takeshi
Central Research Institute of Electric Power Industry
-
Yokoo T
Central Research Institute Of Electric Power Industry
-
OGATA Takanari
Central Research Institute of Electric Power Industry
-
Ogata Takanari
Central Res. Inst. Of Electric Power Ind.
-
Ogata T
Central Research Institute Of Electric Power Industry
-
NAKAMURA Kinya
Central Research Institute of Electric Power Industry
-
MIGNANELLI Michael
AEA Technology plc.
-
Kurata M
Central Research Institute Of Electric Power Industry
関連論文
- Behavior of U-Zr Alloy Containing Simulated Fission Products during Anodic Dissolution in Molten Chloride Electrolyte
- 高速炉用金属燃料における被覆管内面侵食の評価--希土類元素とFe-Cr合金との反応実験
- 金属燃料要素の「常陽」照射試験--試験計画と試験燃料要素設計
- 変化する将来に柔軟に対応するサイクルオプション : 乾式リサイクル技術と金属燃料FBR
- 「常陽」照射試験に向けた金属燃料製造技術の開発--U-20wt%Pu-10wt%Zr合金の射出鋳造
- マイナーアクチニドを含有する高速炉用金属燃料の照射試験--低燃焼度燃料のガス放出率および金相観察
- マイナーアクチニドを含有する高速炉用金属燃料の照射試験--低・中燃焼度燃料ピンの照射後非破壊試験および照射挙動評価
- 金属燃料要素の溶融線出力の評価
- 米国
- 先進燃料サイクルシステムに関する国際会議GLOBAL 2007に参加して
- Recovery of Transuranium Elements from Real High-Level Liquid Waste by Pyropartitioning Process
- Thermodynamic Evaluation of Liquid Cd Cathode Containing U and Pu
- Parametric Survey for Benefit of Partitioning and Transmutation Technology in Terms of High-level Radioactive Waste Disposal
- 電子加速器室内におけるオゾン濃度評価のための計算シミュレーション
- Conversion of Simulated High-level Liquid Waste to Chloride for the Pretreatment of Pyrometallurgical Partitioning Process
- Diffusion of Cerium in Uranium-Zirconium Solid Solutions
- ULOF and UTOP Analyses of a Large Metal Fuel FBR Core Using a Detailed Calculation System
- Sequential Electrolysis of U-Pu Alloy Containing a Small Amount of Am to Recover U- and U-Pu-Am Products
- A Design Study on the FBR Metal Fuel and Core for Commercial Applications
- Reactions of Uranium-Plutonium Alloys with Iron
- Reactions between U - Pu - Zr Alloys and Fe at 923 K
- The Transuranic Mass Balance during the Introduction of Metal Fuel FBR Cycle
- Recovery of Transuranium Elements from Real High-Level Liquid Waste by Pyropartitioning Process
- Development of an Innovative Electrorefiner for High Uranium Recovery Rate from Metal Fast Reactor Fuels
- マイナーアクチニドを含有する高速炉用金属燃料の照射試験--10at.%燃焼度まで照射した燃料ピンの非破壊検査と照射挙動評価
- Development of Fast Reactor Metal Fuels Containing Minor Actinides
- Estimation of Material Balance in Pyrometallurgical Partitioning Process of Transuranic Elements from High-level Liquid Waste
- Single-Stage Extraction Test with Continuous Flow of Molten LiCl-KCl Salt and Liquid Cd for Pyro-Reprocessing of Metal FBR Fuel
- 高速実験炉「常陽」照射試験用金属燃料要素の製造
- 国内における照射試験用金属燃料ピンの製造技術基盤の確立
- Novel Chlorination of Zirconium Dioxide at Low Temperature
- 高速炉用金属燃料における被覆管内面侵食構造の解明
- A Design Study of High Breeding Ratio Sodium Cooled Metal Fuel Core without Blanket Fuels
- A217 「常陽」照射試験用金属燃料の設計と製作(OS8 高温ガス炉・高速炉・金属燃料)