Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Legnaro (PD), Italy; Dipartimento di Ingegneria Industriale, Università di Padova, Padova, PD, Italy.
IRCCS Ospedale Sacro-Cuore Don Calabria, Negrar di Valpolicella, VR, Italy.
Nucl Med Biol. 2022 Jan-Feb;104-105:38-46. doi: 10.1016/j.nucmedbio.2021.11.004. Epub 2021 Nov 26.
Zirconium-89 (Zr) is an emerging radionuclide for positron emission tomography (PET), with nuclear properties suitable for imaging slow biological processes in cellular targets. The Y(p,n)Zr nuclear reaction is commonly exploited as the main production route with medical cyclotrons accelerating low-energy (< 20 MeV) and low-current (< 100 μA) proton beams. Usually, natural yttrium solid targets manufactured by different methods, including yttrium electrodeposition, yttrium sputtering, compressed yttrium powders, and foils, were employed. In this study, the Spark Plasma Sintering (SPS) technique has been investigated, for the first time, to manufacture yttrium solid targets for an efficient Zr radionuclide yield. The natural yttrium disc was bonded to a niobium backing plate using a commercial SPS apparatus and a prototype machine assembled at the University of Pavia. The resulting targets were irradiated in a TR19 cyclotron with a 12 MeV proton beam at 50 μA. A dedicated dissolution module, obtained from a commercial system, was used to develop an automated process for the purification and recovery of the produced Zr radionuclide. The production yield and recovery efficiency were measured and compared to Zr produced by irradiating standard yttrium foils. SPS manufactured targets withstand an average heat power density of approximately 650 W∙cm for continuous irradiation up to 5 h without visible damage. A saturation yield of 14.12 ± 0.38 MBq/μAh was measured. The results showed that the obtained Zr production yield and quality were comparable to similar data obtained using standard yttrium foil targets. In conclusion, the present work demonstrates that the SPS technique might be a suitable technical manufacturing solution aimed at high-yield Zr radioisotope production.
锝-89(Zr)是正电子发射断层扫描(PET)中新兴的放射性核素,其核性质适合对细胞靶标中的缓慢生物过程进行成像。Y(p,n)Zr 核反应通常被用作主要的生产途径,医疗回旋加速器加速低能(<20 MeV)和低电流(<100 μA)质子束。通常,使用不同方法制造的天然钇固体靶,包括钇电沉积、钇溅射、压缩钇粉末和箔片,被用于该反应。在这项研究中,首次研究了火花等离子体烧结(SPS)技术,以制造用于高效 Zr 放射性核素产额的钇固体靶。天然钇圆盘通过商业 SPS 设备和在帕维亚大学组装的原型机与铌背板结合。所得靶在 TR19 回旋加速器中用 12 MeV 质子束在 50 μA 下辐照。使用从商业系统获得的专用溶解模块,开发了一种用于纯化和回收产生的 Zr 放射性核素的自动化过程。测量并比较了生产产量和回收效率与辐照标准钇箔产生的 Zr。SPS 制造的靶能够承受高达 5 小时的连续辐照,平均热功率密度约为 650 W·cm,没有可见的损坏。测量到的饱和产额为 14.12±0.38 MBq/μAh。结果表明,获得的 Zr 生产产量和质量与使用标准钇箔靶获得的类似数据相当。总之,本工作表明 SPS 技术可能是一种适合的高产量 Zr 放射性同位素生产的技术制造解决方案。