The first probe of a FLASH proton beam by PET.

The recently observed FLASH effect related to high doses delivered with high rates has the potential to revolutionize radiation cancer therapy if promising results are confirmed and an underlying mechanism understood. Comprehensive measurements are essential to elucidate the phenomenon. We report the first-ever demonstration of measurements of successive in-spill and post-spill emissions of gammas arising from irradiations by a FLASH proton beam. A small positron emission tomography (PET) system was exposed in an ocular beam of the Proton Therapy Center at MD Anderson Cancer Center to view phantoms irradiated by 3.5 × 1010protons with a kinetic energy of 75.8 MeV delivered in 101.5 ms-long spills yielding a dose rate of 164 Gy s-1. Most in-spill events were due to prompt gammas. Reconstructed post-spill tomographic events, recorded for up to 20 min, yielded quantitative imaging and dosimetric information. These findings open a new and novel modality for imaging and monitoring of FLASH proton therapy exploiting in-spill prompt gamma imaging followed by post-spill PET imaging.

The first PET glimpse of a proton FLASH beam.

We demonstrate the first ever recorded positron-emission tomography (PET) imaging and dosimetry of a FLASH proton beam at the Proton Center of the MD Anderson Cancer Center. Two scintillating LYSO crystal arrays, read out by silicon photomultipliers, were configured with a partial field of view of a cylindrical poly-methyl methacrylate (PMMA) phantom irradiated by a FLASH proton beam. The proton beam had a kinetic energy of 75.8 MeV and an intensity of about 3.5 × 1010protons that were extracted over 101.5 ms-long spills. The radiation environment was characterized by cadmium-zinc-telluride and plastic scintillator counters. Preliminary results indicate that the PET technology used in our tests can efficiently record FLASH beam events. The instrument yielded informative and quantitative imaging and dosimetry of beam-activated isotopes in a PMMA phantom, as supported by Monte Carlo simulations. These studies open a new PET modality that can lead to improved imaging and monitoring of FLASH proton therapy.

Lung Dose Measured on Postradioembolization 90Y PET/CT and Incidence of Radiation Pneumonitis.

Radiation pneumonitis is a rare but possibly fatal side effect of 90Y radioembolization. It may occur 1-6 mo after therapy, if a significant part of the 90Y microspheres shunts to the lungs. In current clinical practice, a predicted lung dose greater than 30 Gy is considered a criterion to exclude patients from treatment. However, contrasting findings regarding the occurrence of radiation pneumonitis and lung dose were previously reported in the literature. In this study, the relationship between the lung dose and the eventual occurrence of radiation pneumonitis after 90Y radioembolization was investigated. Methods: We retrospectively analyzed 317 90Y liver radioembolization procedures performed during an 8-y period (February 2012 to September 2020). We calculated the predicted lung mean dose (LMD) using 99mTc-MAA planar scintigraphy (LMDMAA) acquired during the planning phase and left LMD (LMDY-90) using the 90Y PET/CT acquired after the treatment. For the lung dose computation, we used the left lung as the representative lung volume, to compensate for scatter from the liver moving in the craniocaudal direction because of breathing and mainly affecting the right lung. Results: In total, 272 patients underwent 90Y procedures, of which 63% were performed with glass microspheres and 37% with resin microspheres. The median injected activity was 1,974 MBq (range, 242-9,538 MBq). The median LMDMAA was 3.5 Gy (range, 0.2-89.0 Gy). For 14 procedures, LMDMAA was more than 30 Gy. Median LMDY-90 was 1 Gy (range, 0.0-22.1 Gy). No patients had an LMDY-90 of more than 30 Gy. Of the 3 patients with an LMDY-90 of more than 12 Gy, 2 patients (one with an LMDY-90 of 22.1 Gy and an LMDMAA of 89 Gy; the other with an LMDY-90 of 17.7 Gy and an LMDMAA of 34.1 Gy) developed radiation pneumonitis and consequently died. The third patient, with an LMDY-90 of 18.4 Gy (LMDMAA, 29.1 Gy), died 2 mo after treatment, before the imaging evaluation, because of progressive disease. Conclusion: The occurrence of radiation pneumonitis as a consequence of a lung shunt after 90Y radioembolization is rare (<1%). No radiation pneumonitis developed in patients with a measured LMDY-90 lower than 12 Gy.

Patient-adapted organ absorbed dose and effective dose estimates in pediatric 18F-FDG positron emission tomography/computed tomography studies.

BACKGROUND: Organ absorbed doses and effective doses can be used to compare radiation exposure among medical imaging procedures, compare alternative imaging options, and guide dose optimization efforts. Individual dose estimates are important for relatively radiosensitive patient populations such as children and for radiosensitive organs such as the eye lens. Software-based dose calculation methods conveniently calculate organ dose using patient-adjusted and examination-specific inputs. METHODS: Organ absorbed doses and effective doses were calculated for 429 pediatric 18F-FDG PET-CT patients. Patient-adjusted and scan-specific information was extracted from the electronic medical record and scanner dose-monitoring software. The VirtualDose and OLINDA/EXM (version 2.0) programs, respectively, were used to calculate the CT and the radiopharmaceutical organ absorbed doses and effective doses. Patients were grouped according to age at the time of the scan as follows: less than 1 year old, 1 to 5 years old, 6 to 10 years old, 11 to 15 years old, and 16 to 17 years old. RESULTS: The mean (+/- standard deviation, range) total PET plus CT effective dose was 14.5 (1.9, 11.2-22.3) mSv. The mean (+/- standard deviation, range) PET effective dose was 8.1 (1.2, 5.7-16.5) mSv. The mean (+/- standard deviation, range) CT effective dose was 6.4 (1.8, 2.9-14.7) mSv. The five organs with highest PET dose were: Urinary bladder, heart, liver, lungs, and brain. The five organs with highest CT dose were: Thymus, thyroid, kidneys, eye lens, and gonads. CONCLUSIONS: Organ and effective dose for both the CT and PET components can be estimated with actual patient and scan data using commercial software. Doses calculated using software generally agree with those calculated using dose conversion factors, although some organ doses were found to be appreciably different. Software-based dose calculation methods allow patient-adjusted dose factors. The effort to gather the needed patient data is justified by the resulting value of the characterization of patient-adjusted dosimetry.

Biodistribution and Radiation Dosimetry of 11C-Nicotine from Whole-Body PET Imaging in Humans.

This study assessed the in vivo distribution of 11C-nicotine and the absorbed radiation dose from whole-body 11C-nicotine PET imaging of 11 healthy (5 male and 6 female) subjects. Methods: After an initial CT attenuation scan, 11C-nicotine was administered via intravenous injection. A dynamic PET scan was acquired for 90 s with the brain in the field of view, followed by a series of 13 whole-body PET scans acquired over a 90-min period. Regions of interest were drawn over organs visible in the reconstructed PET images. Time-activity curves were generated, and the residence times were calculated. The absorbed radiation dose for the whole body was calculated by entering the residence time in OLINDA/EXM 1.0 software to model the equivalent organ dose and the effective dose for a 70-kg man. Results: The mean residence times for 11C-nicotine in the liver, red marrow, brain, and lungs were 0.048 ± 0.010, 0.031 ± 0.005, 0.021 ± 0.004, and 0.020 ± 0.005 h, respectively. The mean effective dose for 11C-nicotine was 5.44 ± 0.67 µSv/MBq. The organs receiving the highest absorbed dose from the 11C-nicotine injection were the urinary bladder wall (14.68 ± 8.70 µSv/MBq), kidneys (9.56 ± 2.46 µSv/MBq), liver (8.94 ± 1.67 µSv/MBq), and spleen (9.49 ± 3.89 µSv/MBq). The renal and hepatobiliary systems were the major clearance and excretion routes for radioactivity. Conclusion: The estimated radiation dose from 11C-nicotine administration is relatively modest and would allow for multiple PET examinations on the same subject.