Inorganic Ion Exchange Materials for 90Sr/90Y Generator

描述(申请人提供)：因为它是一款充满活力的纯测试版 半衰期为90天(64.1小时)的发射体 越来越多的人将其作为一种同位素作为辐射源 放射免疫疗法(RIT)。目前获得90Y的流程包括 90锶溶液衰变产生的90Y的提取和提纯 采用液-液萃取工艺。这种同位素是在一种 集中定位并发货给全球用户。 这里建议的发生器将允许生产所需的同位素 在当地的医院或地区性的放射性药房中可以使用它 立刻。第一阶段鉴定出两种无机离子交换材料 装入一头90锶的“奶牛”并“挤奶”以生产无载体的溶液 可立即使用的90Y。在第二阶段，这项技术将进一步 改进并用于发电机的设计，能够提供有用的 每周90Y的数量，化学形式适合于 放射性药物应用。发电机将被制造出来，它的 效果将会得到证明。具有卓越的长期稳定性 无机离子交换剂与有机离子交换材料相比，将是 演示了。 拟议的商业应用：放射免疫疗法，即一种抗体选择性地将放射源直接传递到肿瘤上，通过向肿瘤提供治疗性剂量的辐射，同时最大限度地减少对其他器官的暴露，越来越受到人们的关注。目前，90Y是通过复杂的多步骤工艺生产的，并由中央来源供应，临床医生依赖可靠的供应，以在需要时获得所需的同位素。这里提出的发生器将使90Y像现在的99mTc一样容易获得，并极大地增加这种有价值的疗法的使用。作为替代方案，开发的技术可以在更大范围内使用，以简化目前的90Y生产方法。

DESCRIPTION (provided by applicant): Because it is an energetic pure beta emitter with a half-life on the scale of days (64.1 hr) 90Y is seeing increasing interest as an isotope for use as a radiation source for radioimmunotherapy (RIT). Current processes for obtaining 90Y involve extracting and purifying the 90Y produced by the decay of 90Sr in solution using a liquid-liquid extraction process. The isotope is produced at a centralized location and shipped to users worldwide. The generator proposed here will permit the production of the desired isotope locally in a hospital or regional radiopharmacy where it can be used immediately. Phase I identified two inorganic ion exchange materials that can be loaded with a "cow" of 90Sr and "milked" to produce a carrier-free solution of 90Y ready for immediate use. In Phase II this technology will be further refined and used in the design of a generator capable of delivering a useful quantity of 90Y on a weekly basis in a chemical form suitable for radiopharmaceutical applications. The generator will be fabricated and its efficacy will be demonstrated. The superior long-term stability of the inorganic ion exchanger compared to organic ion exchange materials will be demonstrated. PROPOSED COMMERCIAL APPLICATION: Radioimmunotherapy, where an antibody selectively delivers a radiation source directly to a tumor, is seeing increasing interest as a means of attacking tumors by delivering a therapeutic dose of radiation to the tumor with minimal exposure for other organs. Currently 90Y is produced by a complex multistep process process and supplied from a central source, with clinicians dependent on reliable delivery to have the isotope they need when they need it. The generator proposed here would make 90Y as readily available as 99m Tc is now and greatly increase the use of this valuable therapy. As an alternative, the developed technology could be utilized on a larger scale to simplify the current 90Y production method.