ジルカロイ-2/SUS316Lステンレス鋼の摩擦圧接継手の性能評価
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概要
- 論文の詳細を見る
The development of the friction welded joint between Zircaloy-2 (Zry-2) and Type 316L stainless steel (SUS316L) has been carried out for the fabrication of irradiation capsules with the fuel irradiation test in Japan Materials Testing Reactor (JMTR). As the fabrication test of the Zry-2/SUS316L friction welded joint, the welding condition was determined from the results of total loss and tensile strength. Especially, the joint efficiency of the joint was more than 95% from the tensile tests at R.T. when the friction time was more than 3s. The joint interface was characterized by metallographic observation, elemental analysis and micro-hardness test. It was found that heat-affected zones at the joint interface were different between the center and outside positions, but the thickness of reaction layer was about 5μm. The tensile strength of the joint was equal to that of base Zry-2 metals at 300°C. From the results of these tests, it was obvious that the Zry-2/SUS316L friction welded joints were promised to use for the structural material of irradiation capsules for fuel irradiation tests.
著者
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土谷 邦彦
(独)日本原子力研究開発機構
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北岸 茂
(独)日本原子力研究開発機構
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齋藤 隆
(独)日本原子力研究開発機構
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菊地 泰二
(独)日本原子力研究開発機構
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遠藤 泰一
(独)日本原子力研究開発機構