Pauwels Stanislas, Barone Raffaella, Walrand Stéphan, Borson-Chazot Françoise, Valkema Roelf, Kvols Larry K, Krenning Eric P, Jamar François
Centre de Médecine Nucléaire, Université Catholique de Louvain, Brussels, Belgium.
J Nucl Med. 2005 Jan;46 Suppl 1:92S-8S.
The challenge for internal therapy is to deliver the highest possible dose to the tumor while sparing normal organs from damage. Currently, the potential risk of kidney and red marrow toxicity limits the amount of radioactivity that may be administered. An accurate dosimetry method that would provide reliable dose estimates to these critical organs and to tumors before therapy would allow the clinician to plan a specific therapeutic regimen and also select those patients who would benefit the most from treatment. The dosimetry for (90)Y-1,4,7,10-tetraazacyclododecane-N,N',N'',N'''-tetraacetic acid-d-Phe(1)-Tyr(3)-octreotide is usually based on quantitative imaging at different time points that provides information on activity retention in organs over time and on stylized models representing average individuals. Because the therapeutic agent labeled with (90)Y is not suitable for quantitative imaging, the peptide surrogate labeled with the positron emitter (86)Y can be considered the most appropriate tracer for measuring distribution and retention of the radiopharmaceutical over time. Dose calculations in target organs are generally performed using the MIRDOSE program, in which S values from source to target are integrated. Significant improvement of dose estimates may be achieved by introducing patient-specific adjustments to the standard models. The use of individual kidney volumes assessed by CT instead of the use of a fixed volume for males and females may significantly improve the determination of kidney radiation doses. The use of actual CT-derived tumor volumes has also shown a dose-efficacy relationship. Additional improvements in this field include the validation and use of an (111)In surrogate to avoid the complexity of (86)Y use and the consideration of radiobiologic parameters, such as fractionation effects and the specific biologic efficacy of internally deposited radiation, which are probably underestimated using currently available methods.
内照射治疗面临的挑战是在使正常器官免受损伤的同时,尽可能向肿瘤输送高剂量的药物。目前,肾脏和红骨髓毒性的潜在风险限制了可给予的放射性剂量。一种准确的剂量测定方法,能够在治疗前为这些关键器官和肿瘤提供可靠的剂量估计,这将使临床医生能够制定具体的治疗方案,并挑选出那些从治疗中获益最大的患者。钇-90标记的1,4,7,10-四氮杂环十二烷-N,N',N'',N'''-四乙酸-d-苯丙氨酸(1)-酪氨酸(3)-奥曲肽的剂量测定通常基于不同时间点的定量成像,该成像可提供随时间推移器官内放射性滞留的信息,以及基于代表普通个体的理想化模型。由于钇-90标记的治疗剂不适用于定量成像,因此正电子发射体钇-86标记的肽替代物可被视为测量放射性药物随时间分布和滞留的最合适示踪剂。靶器官的剂量计算通常使用MIRDOSE程序,该程序对从源器官到靶器官的S值进行积分。通过对标准模型进行患者特异性调整,可显著改善剂量估计。使用CT评估的个体肾脏体积,而非采用男女固定体积,可能会显著改善肾脏辐射剂量的测定。使用实际CT得出的肿瘤体积也显示出剂量-疗效关系。该领域的其他改进包括验证和使用铟-111替代物,以避免使用钇-86的复杂性,以及考虑放射生物学参数,如分次照射效应和体内沉积辐射的特定生物学效应,目前可用方法可能低估了这些效应。