Mechanical Properties of Fusion Reactor First Wall Candidate Material JLF1

聚变反应堆第一壁候选材料 JLF1 的机械性能

• 批准号: 09680487
• 负责人: KOHNO Yutaka
• 金额: $ 1.41万
• 依托单位: The University of Tokyo
• 依托单位国家: 日本
• 项目类别: Grant-in-Aid for Scientific Research (C)
• 财政年份: 1997
• 资助国家: 日本
• 起止时间: 1997 至 1998
• 项目状态: 已结题
• 来源: https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-09680487/
• 关键词: JLF1 Steel; Ferritic; Martensitic steel; Fusion Reactor First Wall Material; Low Activation Steel; Irradiation Embrittlement; Neutron Irradiation; Charpy test; Tensil test; 0.2%耐力; 照射硬化; JLF1鋼; 延性脆性遷移温度; 微小試験片; 引張り試験

Mechanical property changes of JLF1 low activation ferritic/martensitic steel (Fe-9Cr-2W-0.2V-Ta) after heavy neutron irradiation were widely investigated using small size specimens (l.5 mm CVN, l/3 CVN, SSJ-tensile, W-tensile). One of the most important problems in irradiated ferritic/martensitic steel is increase of the ductile-to-brittle transition temperature (DBTT). DBTT increase in JLF1 after neutron irradiation up to 6Odpa was estimated to be still below room temperature, and the highest DBTT was measured to be 255K following irradiation of about 25dpa. There was no clear specimen size dependence in DBTT.Results of tensile tests using SSJ and/or W specimens showed that 0.2% proof stress of JLF1 once increased with irradiation up to 15-20dpa followed by the decrease with further irradiation. This results indicated that there was a maximum of 0.2% proof stress around 15-20dpa, and that dose dependence of DBTT was closely related to that of 0.2% proof stress. This means that the change of DBTT in JLF1 is considered to be mainly caused by hardening mechanism due to irradiation.

用小尺寸试件(1.5 mm CVN、L/3CVN、SSJ拉伸、W拉伸)研究了JLF1低活性铁素体/马氏体钢(Fe-9Cr-2W-0.2V-Ta)经重中子辐照后力学性能的变化。辐照铁素体/马氏体钢的一个重要问题是韧脆转变温度(DBTT)的提高。经60dpa的中子辐照后，JLF1的DBTT增加估计仍低于室温，约25dpa的辐照后，DBTT的最高值为255K。用SSJ和/或W试件进行的拉伸试验结果表明，JLF1的0.2%验证应力在辐照至15-20dpa时一度增加，然后随着辐照的进一步降低而减小。结果表明，在15-20dpa范围内存在最大0.2%的保护应力，且DBTT的剂量依赖关系与0.2%的保护应力密切相关。这意味着JLF1的DBTT变化被认为主要是由辐照硬化机制引起的。