钛合金作为高强度质子加速器束流窗口材料的辐射损伤研究

T. Ishida, E. Wakai, S. Makimura, P. Hurh, K. Ammigan, A. Casella, David Edwards, D. Senor, C. Densham, M. Fitton, J. Bennett, Dohyun Kim, N. Simos, M. Calviani, C. Martin
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引用次数: 6

摘要

高强度双α + β相钛合金Ti-6Al-4V在几个加速器目标设施中用作束窗材料。然而,对于高强度质子束辐照如何影响这种合金的材料性能,人们所知相对较少。随着计划将J-PARC和费米实验室的中微子设施升级到超过1兆瓦的束流功率,窗口材料的辐射损伤将达到每年几个原子位移(dpa),大大高于现有数据的~0.3 dpa水平。辐射合作已经在BLIP设施进行了各种目标和窗口材料样品的高强度质子束辐照,包括各种钛合金。照射后,正在对第一个胶囊内的标本进行检查,辐照强度高达0.25 dpa。PNNL的热室拉伸试验显示Ti-6Al-4V具有明显的辐射硬化和塑性损失特征,而Ti-3Al-2.5V具有较少的β相,其硬化程度较轻。接下来将进行显微组织研究,以研究这些合金之间拉伸性能差异的原因。高周疲劳(HCF)性能是估计脉冲质子束周期性热应力下束流窗寿命的关键。辐照钛合金的第一个HCF数据将通过费米实验室的常规弯曲疲劳试验和Culham实验室的超声中尺度疲劳试验获得。第二个胶囊中的样品,辐射强度高达~ 1dpa,覆盖了典型的钛合金等级,包括可能抗辐射的候选材料。这些对钛合金辐射损伤影响的系统研究旨在使我们能够预测Ti-6Al-4V制成的电流束窗的实际寿命,并通过选择更耐辐射和热冲击的合金来延长寿命。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Radiation Damage Studies on Titanium Alloys as High Intensity Proton Accelerator Beam Window Materials
A high-strength dual alpha+beta phase titanium alloy Ti-6Al-4V is utilized as a material for beam windows in several accelerator target facilities. However, relatively little is known about how material properties of this alloy are affected by high-intensity proton beam irradiation. With plans to upgrade neutrino facilities at J-PARC and Fermilab to over 1 MW beam power, the radiation damage in the window material will reach a few displacements per atom (dpa) per year, significantly above the ~0.3 dpa level of existing data. The RaDIATE collaboration has conducted a high intensity proton beam irradiation of various target and window material specimens at BLIP facility, including a variety of titanium alloys. Post-Irradiation Examination of the specimens in the 1st capsule, irradiated at up to 0.25 dpa, is in progress. Tensile tests in a hot cell at PNNL exhibited a clear signature of radiation hardening and loss of ductility for Ti-6Al-4V, while Ti-3Al-2.5V, with less beta phase, exhibited less severe hardening. Microstructural investigations will follow to study the cause of the difference in tensile behavior between these alloys. High-cycle fatigue (HCF) performance is critical to the lifetime estimation of beam windows exposed to a periodic thermal stress from a pulsed proton beam. The 1st HCF data on irradiated titanium alloys are to be obtained by a conventional bend fatigue test at Fermilab and by an ultrasonic mesoscale fatigue test at Culham Laboratory. Specimens in the 2nd capsule, irradiated at up to ~1 dpa, cover typical titanium alloy grades, including possible radiation-resistant candidates. These systematic studies on the effects of radiation damage of titanium alloys are intended to enable us to predict realistic lifetimes of current beam windows made of Ti-6Al-4V and to extend the lifetime by choosing a more radiation and thermal shock tolerant alloy.
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