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- Dewaraja, Y. K., et al.
(author)
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MIRD Pamphlet No. 23: Quantitative SPECT for Patient-Specific 3-Dimensional Dosimetry in Internal Radionuclide Therapy
- 2012
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In: Journal of Nuclear Medicine. - : Society of Nuclear Medicine. - 0161-5505 .- 2159-662X. ; 53:8, s. 1310-1325
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Journal article (peer-reviewed)abstract
- In internal radionuclide therapy, a growing interest in voxel-level estimates of tissue-absorbed dose has been driven by the desire to report radiobiologic quantities that account for the biologic consequences of both spatial and temporal nonuniformities in these dose estimates. This report presents an overview of 3-dimensional SPECT methods and requirements for internal dosimetry at both regional and voxel levels. Combined SPECT/CT image-based methods are emphasized, because the CT-derived anatomic information allows one to address multiple technical factors that affect SPECT quantification while facilitating the patient-specific voxel-level dosimetry calculation itself. SPECT imaging and reconstruction techniques for quantification in radionuclide therapy are not necessarily the same as those designed to optimize diagnostic imaging quality. The current overview is intended as an introduction to an upcoming series of MIRD pamphlets with detailed radionuclide-specific recommendations intended to provide best-practice SPECT quantification-based guidance for radionuclide dosimetry.
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| 4. |
- Taldone, Tony, et al.
(author)
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Radiosynthesis of the iodine-124 labeled Hsp90 inhibitor PU-H71
- 2016
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In: Journal of labelled compounds & radiopharmaceuticals. - : WILEY-BLACKWELL. - 0362-4803 .- 1099-1344. ; 59:3, s. 129-132
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Journal article (peer-reviewed)abstract
- Heat shock protein 90 (Hsp90) is an ATP dependent molecular chaperone protein whose function is critical for maintaining several key proteins involved in survival and proliferation of cancer cells. PU-H71 (1), is a potent purine-scaffold based ATP pocket binding Hsp90 inhibitor which has been shown to have potent activity in a broad range of in vivo cancer models and is currently in Phase I clinical trials in patients with advanced solid malignancies, lymphomas, and myeloproliferative neoplasms. In this report, we describe the radiosynthesis of [I-124]-PU-H71(5); this was synthesized from the corresponding Boc-protected stannane precursor 3 by iododestannylation with [I-124]-NaI using chloramine-T as an oxidant for 2min, followed by Boc deprotection with 6 N HCl at 50 degrees C for 30min to yield the final compound. The final product 5 was purified using HPLC and was isolated with an overall yield of 55 +/- 6% (n=6, isolated) from 3, and >98% purity and an average specific activity of 980mCi/mu mol. Our report sets the stage for the introduction of [I-124]-PU-H71 as a potential non-invasive probe for understanding biodistribution and pharmacokinetics of PU-H71 in living subjects using positron emission tomography imaging.
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| 5. |
- Yonekura, Y, et al.
(author)
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ICRP Publication 140: Radiological Protection in Therapy with Radiopharmaceuticals.
- 2019
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In: Annals of the ICRP. - : SAGE Publications. - 1872-969X .- 0146-6453. ; 48:1, s. 5-95
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Journal article (peer-reviewed)abstract
- Radiopharmaceuticals are increasingly used for the treatment of various cancers with novel radionuclides, compounds, tracer molecules, and administration techniques. The goal of radiation therapy, including therapy with radiopharmaceuticals, is to optimise the relationship between tumour control probability and potential complications in normal organs and tissues. Essential to this optimisation is the ability to quantify the radiation doses delivered to both tumours and normal tissues. This publication provides an overview of therapeutic procedures and a framework for calculating radiation doses for various treatment approaches. In radiopharmaceutical therapy, the absorbed dose to an organ or tissue is governed by radiopharmaceutical uptake, retention in and clearance from the various organs and tissues of the body, together with radionuclide physical half-life. Biokinetic parameters are determined by direct measurements made using techniques that vary in complexity. For treatment planning, absorbed dose calculations are usually performed prior to therapy using a trace-labelled diagnostic administration, or retrospective dosimetry may be performed on the basis of the activity already administered following each therapeutic administration. Uncertainty analyses provide additional information about sources of bias and random variation and their magnitudes; these analyses show the reliability and quality of absorbed dose calculations. Effective dose can provide an approximate measure of lifetime risk of detriment attributable to the stochastic effects of radiation exposure, principally cancer, but effective dose does not predict future cancer incidence for an individual and does not apply to short-term deterministic effects associated with radiopharmaceutical therapy. Accident prevention in radiation therapy should be an integral part of the design of facilities, equipment, and administration procedures. Minimisation of staff exposures includes consideration of equipment design, proper shielding and handling of sources, and personal protective equipment and tools, as well as education and training to promote awareness and engagement in radiological protection. The decision to hold or release a patient after radiopharmaceutical therapy should account for potential radiation dose to members of the public and carers that may result from residual radioactivity in the patient. In these situations, specific radiological protection guidance should be provided to patients and carers.
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