Swelling Behaviors in a Fuel Assembly for the Wrapping Wire and Duct Made of Modified 316 Austenitic Stainless Steel
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概要
- 論文の詳細を見る
Swelling behaviors in the wrapping wire and duct made of modified type 316 austenitic stainless steel were investigated in a fuel assembly irradiated in a fast breeder reactor. The temperature dependence of volumetric swelling was measured in the wrapping wire and the duct, and the peak temperatures of swelling were evaluated. The void distribution in the material was measured by microstructure observation with electron microscopy, and it was found that the voids prefentially grew near the surface. This phenomenon seemed to be caused by a surface effect on the neutron-irradiated materials.
- 一般社団法人 日本原子力学会の論文
- 2010-10-01
著者
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Yamagata Ichiro
Oarai Research And Development Center Japan Atomic Energy Agency
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AKASAKA Naoaki
Oarai Research and Development Center, Japan Atomic Energy Agency
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Akasaka Naoaki
Oarai Research And Development Center Japan Atomic Energy Agency
関連論文
- Effects of Microstructural Evolution on Charpy Impact Properties of Modified Ferritic/Martensitic Steel after Neutron Irradiation
- Mechanical Behavior of Oxide Dispersion Strengthened Steels Irradiated in JOYO
- Effects of Fast Reactor Irradiation Conditions on Tensile and Transient Burst Properties of Ferritic/Martensitic Steel Claddings
- Swelling Behaviors in a Fuel Assembly for the Wrapping Wire and Duct Made of Modified 316 Austenitic Stainless Steel