This study proposes a predictive monitoring method for irradiation assisted stress corrosion cracking (IASCC) of austenitic stainless steels. High purity model austenitic stainless steel s were irradiated up to ldpa or 5dpa in JRR-3. IASCC susceptibility of the irradiated specimens was determined by scanning electro microscopy (SEM) on fractured surface of the specimens after slow strain rate tensile (SSRT) testing in high temperature water simulating boiling water reactor (BWR) conditions. Magnetic proper...
英字タイトル:
A Study of Testing Method for Predictive-Monitoring of IASCC Susceptibility

The remote operated vibrating sample magnetometer (VSM) for neutron irradiated samples has been developed. The maximum range of applied magnetic field is more t han ￡0.5/10 A/m, and the resolution of magnetization is higher than 5 x10-A'm2. The magnetization curves of neutron irradiated samples were measured by this VSM , and the relationships between dose, which is one of representative irradiation parameter, and magnetic properties such as magnetic coercive force. As result, it was revealed that there a...
英字タイトル:
Development of Remote Operated Vibrating Sample Magnetometerfor Evaluation of Irradiation Damage

エネルギー資源に乏しい我が国では、海外からの化石資源の依存度を下げ、さらに地球温暖化問題解決に向けて二酸化炭素の排出量を低減するために、安全性の確保を大前提として原子力エネルギーの利用を進めることを基本方針としている。高温ガス炉は、ヘリウムガスタービンによる高効率発電、水素製造、さらにはガスタービンの廃熱を利用した海水淡水化等の多様な産業利用に応えることができる原子炉である。 2018 年 7 月に閣議決定された第 5 次エネルギー基本計画の「第 3 節技術開発の推進 2．取り組むべき技術課題」においては、「水素製造を含めた多様な産業利用が見込まれ、固有の安全性を有する高温ガス炉など、安全性の高度化に貢献する技術開発を、海外市場の動向を見据えつつ国際協力の下で推進する」と記載されている。 原子力機構は、茨城県大洗町に日本初の高温ガス炉高温工学試験研究炉（ HTTR : High Temperature engineering Test Reactor）を国産技術により建設し、2004 年に 950 ℃の熱を取り出すことに世界で唯一成功、2010 年に 950 ℃で 50 日間の連続運転により、安定に高温核熱を...

To realize long-life fast breeder reactor (FBR) plants, it is important to develop a precise estimation method of metallurgical microstruct ure change before crack initiation. For estimating the metallurgical microstructure change related to degradation in commercial FBR plants, the change of magnetic property is focused on. Austenitic stainless steel is paramagnetic, but the magnetic flux density changes as creep damage at 773K or 823K. Finally, it is possible to detect the metallurgical microstructure c...
英字タイトル:
Magnetic change in austenitic stainless steels subjected to long term creep damage

Proper management of neutron irradiation damage on structural materials is important to ensure the Lealth of long-life fast breeder reactor (FBR) plants. Therefore, the effective index f or irradiation amage or the combination of those should be developed. In this study, the effects of dose, helium, nd the ratio of helium to dose on tensile and creep properties of FBR gra de type 316 stainless steel were investigated in the assumed irradiation damage range of FBR structural materials, that is, up to bout 1...
英字タイトル:
R & D on Irradiation Damage Management Technology for FBR Structural Materials 髙屋 茂 Shigeru TAKAYA