Radiation precautions for inpatient and outpatient 177Lu-DOTATATE peptide receptor radionuclide therapy of neuroendocrine tumours

Radiation Exposure to Patients and Others During Therapy for Pediatric Neuroblastoma With Lu-177-DOTATATE

PURPOSE

This study evaluated Lutetium-177-(DOTA°,Tyr 3 ) octreotate (Lu-177-DOTATATE) clearance in pediatric patients with neuroblastoma and assessed the effective doses received by patients, family caregivers, and medical staff during therapy.

PATIENTS AND METHODS

Twenty-three children (3-13 y) who received Lu-177-DOTATATE between 2023 and 2024 were enrolled. External dose rates were measured at 0, 1, 2, 4, 6, 24, 48, and 96 hours post-administration to estimate patients' Lu-177-DOTATATE retention rate, the effective half-life, and the maximum cumulative effective dose around patients. Whole-body and red-marrow absorbed doses were calculated based on multi-time-point whole-body planar and SPECT/CT imaging using HERMES Dosimetry software. Whole-body effective doses to family caregivers and medical personnel were measured using thermoluminescence dosimeters (TLDs), and effective finger doses for medical staff were measured using ring TLDs.

RESULTS

The mean administered activity was 3.687±1.545 (range, 1.469-7.368) GBq. Whole-body retention rates at 1-96 hours post-administration ranged from 72.0% to 10.0%, with 99% clearance expected within 11 days. Clearance followed a biexponential decay model, with estimated effective half-lives of 1.4±0.8 and 52.3±18.6 hours for the fast and slow phases, respectively, at 2 m. Estimated maximum cumulative effective doses (within 11 days) at 1 and 2 m were 0.442±0.174 and 0.138±0.058 mSv, respectively. Absorbed doses for children were 0.159±0.076 mGy/MBq (whole body) and 0.611±0.416 mGy/MBq (red-marrow). Whole-body effective doses to family caregivers averaged 0.245±0.063 (range, 0.150-0.390) mSv. The whole-body and finger-effective doses to the radiopharmacists were 3.7±1.8 and 155.3±73.0 μSv/patient, respectively. The mean of whole-body and the median ( P25 , P75 ) of finger-effective doses to nurses were 4.7±1.4 μSv/patient and 16.7 (10, 470) μSv/patient, respectively.

CONCLUSIONS

Lu-177-DOTATATE was rapidly cleared in children with neuroblastoma. Radiation exposure to others was below personal dose limits.

Factors and predictors affecting late external dose rates and isolation period in patients after lutetium-177-labeled DOTA-Tyr3-octreotate treatment for neuroendocrine tumors

OBJECTIVE

In peptide receptor radionuclide therapy (PRRT) using lutetium-177-labeled DOTA-Tyr3-octreotate ([177Lu] DOTATATE), isolation is required until the external dose rate at 1 m (EDR-1 m) from the body surface falls below the regulatory standards of each country. While it is known that renal function influences EDR-1 m reduction within 180 min post-administration, the factors affecting EDR-1 m on the day following administration (Late EDR-1 m) remain unclear. This study aimed to identify factors influencing Late EDR-1 m after PRRT using [177Lu] DOTATATE for neuroendocrine tumors and to predict Late EDR-1 m using pretreatment [111In] pentetreotide single-photon emission computed tomography/computed tomography (SPECT/CT) data.

METHODS

This study analyzed 111 PRRT cycles administered to 36 patients between September 2021 and August 2024. Late EDR-1 m was set as the dependent variable, whereas total radiopharmaceutical uptake (LUTtotal), dose per body weight, creatinine clearance (CCr), and albumin-bilirubin (ALBI) score were set as the independent variables in the multiple regression analysis. LUTtotal was calculated using SPECT/CT data acquired after the patient left the radiation therapy room, defining the volume of interest (VOI) as the area with SUVmean + 2SD or higher in the skeletal muscle. The VOI volume multiplied by the SUVmean was used to define LUTtotal. In addition, using [111In] pentetreotide SPECT/CT data, the total radiopharmaceutical uptake (OCTtotal) was calculated in a manner similar to LUTtotal, and its correlation with LUTtotal was examined. A predictive equation for Late EDR-1 m was developed using the results of the multivariate analysis, and its performance was tested using subsequent cases between August 2024 and January 2025.

RESULTS

The median measured Late EDR-1 m was 8.0 (range, 4.0-26.0) μSv/h. LUTtotal and dose per body weight were significantly correlated with Late EDR-1 m, whereas CCr and ALBI scores were not. Based on the results of the multivariate analysis, the predictive equation using the dose per body weight, assuming a dosage of 7400 MBq and OCTtotal, achieved a root mean square error (RMSE) of 2.24 μSv/h. In subsequent test cases, the RMSE was 3.47 μSv/h.

CONCLUSIONS

Late EDR-1 m is significantly correlated with LUTtotal and dose per body weight. It can be accurately predicted using [111In] pentetreotide SPECT/CT data.

Lutetium-177 Therapy in Italy: Environmental Impact Assessment in Anticipation of Its Widespread Use in Prostate Cancer Treatment

ABSTRACT

This article addresses the evolving state of lutetium-177 radiopharmaceutical therapies in Italy, focusing on the importance of the definition of patient management practices regarding the approved treatments based on [ 177 Lu]Lu-DOTATATE for neuroendocrine tumors and [ 177 Lu]Lu-PSMA-617 for metastatic castration-resistant prostate cancer. Italian medical facilities are facing new challenges with the increase in the demand for such therapies while transitioning from restrictive hospitalization requirements to more flexible outpatient options. Therefore, four management strategies are described here, varying from immediate discharge after the administration to 24-h hospitalization, and their environmental and radiation safety implications are evaluated through simple models aimed at assessing the effective doses on the local population and wastewater purification plant workers. Results show that, while higher effective doses may be caused by an immediate discharge-based modality, they remain within acceptable limits, particularly when dealing with a smaller number of patients. Prolonged hospitalizations guarantee superior radiation safety levels but might not be sustainable with the expected increase in patient volumes in the future.

Harmonization of practice of release of patients after radiopharmaceutical therapy

The implementation of novel therapeutic radiopharmaceuticals requires developing, updating, and harmonizing requirements for radiation safety in radiopharmaceutical therapy (RPT). Public exposure from patients with administered radiopharmaceuticals and biological radioactive waste management have been identified as the main problems in RPT. The aim of our study was to compare different approaches to the development of patient release criteria after RPT with different radiopharmaceuticals, considering radiation exposure of members of the public in transport, biological elimination of radionuclides from a patient's body, and the generation of biological waste. The study was performed for the following radiopharmaceuticals:177Lu-PSMA-617,177Lu-DOTATATE, Na131I,131I-mIBG, and153Sm-oxabifor. Two base approaches to patient release criteria were considered. The first approach is based on the radioactive decay of radionuclides and is divided into two groups: considering one radiopharmaceutical administration and considering several radiopharmaceutical administrations per course. The second approach is based on the radioactive decay of radionuclides and biological elimination of radiopharmaceuticals from the patient's body (effective half-life) and is divided into groups based on 1 and 5 mSv dose constraints per course. The ffective dose rates from patients and sewage tanks to passengers and staff on public transport were estimated for various scenarios of patients traveling after RPT. The results demonstrated that the radiation safety of members of the public in transport should be considered when establishing the release criteria of patients after RPT. Based on the results, it is recommended to follow the approach based on the radioactive decay of radionuclides and dose constraints to members of the public in contact with patients of 1 mSv per radiopharmaceutical administration, and keep patients in the nuclear medicine department after radiopharmaceutical administration for at least 4-6 h. The patient release criteria defined according to this approach comply with patient release criteria used in different countries, and allow the radiation safety of the public to be maintained.

A Monte Carlo study comparing dead-time losses of a gamma camera between tungsten functional paper and lead sheet for dosimetry in targeted radionuclide therapy with Lu-177

OBJECTIVE

Dead-time loss is reported to be non-negligible for some patients with a high tumor burden in Lu-177 radionuclide therapy, even if the administered activity is 7.4 GBq. Hence, we proposed a simple method to shorten the apparent dead time and reduce dead-time loss using a thin lead sheet in previous work. The collimator surface of the gamma camera was covered with a lead sheet in our proposed method. While allowing the detection of 208-keV gamma photons of Lu-177 that penetrate the sheet, photons with energies lower than 208 keV, which cause dead-time loss, were shielded. In this study, we evaluated the usefulness of tungsten functional paper (TFP) for the proposed method using Monte Carlo simulation.

METHODS

The count rates in imaging of Lu-177 administered to patients were simulated with the International Commission on Radiological Protection (ICRP) 110 phantom using the GATE Monte Carlo simulation toolkit. The simulated gamma cameras with a 0.5-mm lead sheet, 1.2-mm TFP, or no filter were positioned closely on the anterior and posterior sides of the phantom. The apparent dead times and dead-time losses at 24 h after administration were calculated for an energy window of 208 keV ± 10%. Moreover, the dead-time losses at 24-120 h were analytically assessed using activity excretion data of Lu-177-DOTATATE.

RESULTS

The dead-time loss without a filter was 5% even 120 h after administration in patients with a high tumor burden and slow excretion, while those with a lead sheet and TFP were 0.22 and 0.58 times less than those with no filter, respectively. The count rates with the TFP were 1.3 times higher than those with the lead sheet, and the TFP could maintain primary count rates at 91-94% of those without a filter.

CONCLUSIONS

Although the apparent dead time and dead-time loss with the lead sheet were shorter and less than those with TFP, those with TFP were superior to those without a filter. The advantage of TFP over the lead sheet is that the decrease in primary count rates was less.

Prediction of 1 cm dose-equivalent rate on the day after administration of 177Lu-DOTATATE from 111In-somatostatine receptor scintigraphy prior to treatment

OBJECTIVE

When patients administered 177Lu-DOTATATE are released or discharged from rooms where radiopharmaceuticals are used, the time required for release or discharge varies across patients. This study investigated whether the amount of radioactivity accumulated on 111In-somatostatine receptor scintigraphy (111In-SRS) performed prior to treatment can predict the 1 cm dose-equivalent rate at a distance of 1 m from the patient on the day after 177Lu-DOTATATE administration.

METHODS

Whole-body planar 111In-SRS images were acquired for 21 patients. Pixel values within whole-body and abdominal (35 × 25 cm) regions of interest (ROIs) were converted to radioactivity dose (MBq). The 1 cm dose-equivalent rate (µSv/h) at a distance of 1 m from the patient 18.3 ± 0.5 h after administration of 177Lu-DOTATATE was measured using an ionization survey meter.

RESULTS

The following relationships were observed between the radioactivity on 111In-SRS and the 1 cm dose-equivalent rate on the day after administration of 177Lu-DOTATATE: whole-body ROI: y = 0.16x + 5.01 (r = 0.56, p = 0.009), abdominal ROI: y = 0.27x + 5.13 (r = 0.63, p = 0.002). The regression equations indicate that patients cannot be released or discharged from the radiopharmaceutical room the day after 177Lu-DOTATATE administration if the whole-body and abdominal ROI doses are greater than 81 and 48 MBq, respectively, on 111In-SRS.

CONCLUSIONS

The amount of radioactivity accumulated on 111In-SRS may be a predictor of release criteria for patients receiving 177Lu-DOTATATE.

Preliminary Study on Lutetium-177 and Gold Nanoparticles: Apoptosis and Radiation Enhancement in Hepatic Cancer Cell Line

This study investigates a novel approach toward enhancing the efficacy of Lutetium-177 (Lu-177) radiopharmaceutical therapy by combining it with gold nanoparticles (AuNPs) in the HepG2 hepatic cancer cell line. Lu-177, known for its effective β radiation, also emits gamma rays at energies (113 keV and 208 keV) near the photoelectric absorption range, suggesting potential for targeted and localized radiation enhancement when used in conjunction with AuNPs. Thus, HepG2 cells were treated at two different activity levels (74 MBq and 148 MBq), with Lu-177 alone, with a combination of Lu-177 and AuNPs in two sizes (10 nm and 50 nm), while some received no treatment. Treatment efficacy was assessed by quantifying the radiation enhancement ratio (RER) and the apoptosis levels. The results reveal that combining Lu-177 with AuNPs significantly increases cell death and apoptosis compared to Lu-177 alone, with 10 nm AuNPs demonstrating superior effectiveness. Additionally, varying Lu-177 activity levels influenced the treatment outcomes, with higher activity levels further augmenting the therapeutic impact of combined therapy. These findings underscore the potential of utilizing Lu-177's beta, but also gamma, emissions, traditionally considered non-therapeutic, for localized radiation enhancement when combined with AuNPs. This novel strategy leverages Lu-177 as an internal irradiator to exploit gamma radiation for a targeted therapeutic advantage without requiring nanoparticle functionalization. The study provides a promising approach to improving radionuclide therapy and sets the stage for future research aimed at optimizing cancer treatments through the combined use of Lu-177 and AuNPs.

Radiomics Analysis for Clinical Decision Support in 177Lu-DOTATATE Therapy of Metastatic Neuroendocrine Tumors using CT Images

Background

Radiomics is the computation of quantitative image features extracted from medical imaging modalities to help clinical decision support systems, which could ultimately meliorate personalized management based on individual characteristics.

Objective

This study aimed to create a predictive model of response to peptide receptor radionuclide therapy (PRRT) using radiomics computed tomography (CT) images to decrease the dose for patients if they are not a candidate for treatment.

Material and Methods

In the current retrospective study, 34 patients with neuroendocrine tumors whose disease is clinically confirmed participated. Effective factors in the treatment were selected by eXtreme gradient boosting (XGBoost) and minimum redundancy maximum relevance (mRMR). Classifiers of decision trees (DT), random forest (RF), and K-nearest neighbors (KNN) with selected quantitative and clinical features were used for modeling. A confusion matrix was used to evaluate the performance of the model.

Results

Out of 866 quantitative and clinical features, nine features with the XGBoost method and ten features with the mRMR pattern were selected that had the most relevance in predicting response to treatment. Selected features of the XGBoost method in integration with the RF classifier provided the highest accuracy (accuracy: 89%), and features selected by the mRMR method in combination with the RF classifier showed satisfactory performance (accuracy: 74%).

Conclusion

This exploratory analysis shows that radiomic features with high accuracy can effectively predict response to personalize treatment.

The heterobivalent (SSTR2/albumin) radioligand [67Cu]Cu-NODAGA-cLAB4-TATE enables efficient somatostatin receptor radionuclide theranostics

Somatostatin type 2 receptor (SSTR2) radionuclide therapy using β- particle-emitting radioligands has entered clinical practice for the treatment of neuroendocrine neoplasms (NENs). Despite the initial success of [177Lu]Lu‑DOTA-TATE, theranostic SSTR2 radioligands require improved pharmacokinetics and enhanced compatibility with alternative radionuclides. Consequently, this study evaluates the pharmacokinetic effects of the albumin-binding domain cLAB4 on theranostic performance of copper‑67-labeled NODAGA-TATE variants in an SSTR2-positive mouse pheochromocytoma (MPC) model. Methods: Binding, uptake, and release of radioligands as well as growth-inhibiting effects were characterized in cells grown as monolayers and spheroids. Tissue pharmacokinetics, absorbed tumor doses, and projected human organ doses were determined from quantitative SPECT imaging in a subcutaneous tumor allograft mouse model. Treatment effects on tumor growth, leukocyte numbers, and renal albumin excretion were assessed. Results: Both copper‑64- and copper‑67-labeled versions of NODAGA-TATE and NODAGA-cLAB4‑TATE showed similar SSTR2 binding affinity, but faster release from tumor cells compared to the clinical reference [177Lu]Lu‑DOTA-TATE. The bifunctional SSTR2/albumin-binding radioligand [67Cu]Cu‑NODAGA-cLAB4‑TATE showed both an improved uptake and prolonged residence time in tumors resulting in equivalent treatment efficacy to [177Lu]Lu‑DOTA-TATE. Absorbed doses were well tolerated in terms of leukocyte counts and kidney function. Conclusion: This preclinical study demonstrates therapeutic efficacy of [67Cu]Cu‑NODAGA-cLAB4‑TATE in SSTR2-positive tumors. As an intrinsic radionuclide theranostic agent, the radioligand provides stable radiocopper complexes and high sensitivity in SPECT imaging for prospective determination and monitoring of therapeutic doses in vivo. Beyond that, copper‑64- and copper‑61-labeled versions offer possibilities for pre- and post-therapeutic PET. Therefore, NODAGA-cLAB4-TATE has the potential to advance clinical use of radiocopper in SSTR2-targeted cancer theranostics.

Dosimetric Considerations for 177 Lu-DOTATATE Therapy in a Patient With Chronic Renal Failure Under Hemodialysis

ABSTRACT

This case report explores the use of 177 Lu-DOTATATE in a hemodialysis patient. For the first time, this study assesses the average dose received by the bone marrow, the primary organ at risk, using an original double estimation method through independently acquired imaging and biological samples counting data. Despite elevated doses, the absorbed doses to the bone marrow (0.662-0.740 Gy) were within safe limits. Radiation protection measurements for staff were also compliant. This work supports that effective early dialysis and systematic personalized dosimetry are crucial for hemodialysis patients undergoing 177 Lu-PRRT due to their variability (residual excretion, treatment history, etc).

Radiation Safety Assessment of 177Lu-DOTATATE Intra-arterial Peptide Receptor Therapy (PRRT)

Objective

177Lu-DOTATATE peptide receptor therapy (PRRT) is an established treatment for patients suffering from neuroendocrine tumors. In the last few years, intra-arterial PRRT is being considered for patients having liver metastatic disease predominantly. The aim of our study is to measure the radiation doses received by the treating intervention radiologists involved in intra-arterial PRRT treatment using 177Lu-DOTATATE.

Materials and Methods

Radiation safety-related data of 31 patients who underwent 177Lu-DOTATATE intra-arterial PRRT treatment were used for this study. The exposure rate was measured at the hand and eye and chest level of treating intervention radiologists continuously from the beginning to the end of the administration. Exposure from the patient at the body surface (at the level of liver, thigh, and extremities) and 1 m from the body surface was measured just after the administration. The mean radiation exposure from the patient at the body surface and 1 m from the body was also calculated.

Results

The mean administered activity was found to be 194 (±17) mCi. The mean radiation exposure at the surface at the level of the liver, thigh, and feet and at 1 m from the surface was found to be 100 (±25.11), 9 (±1.27), 5.6 (±0.52), and 5.3± (0.50) μSv/hr, respectively. The mean administration time was found to be 23 ± 5.6 min. The mean radiation dose to the hands, and eyes, of the treating intervention radiologist per procedure, was found to be 6.425 ± 2.75 μSv, 5.43 ± 1.76 μSv and 1-m exposure from the patient was found to be 5.3 ± 0.246 μSv, respectively.

Conclusion

Our result shows that the radiation exposure from the patient postadministration is below the permissible limit of discharge. The radiation exposure to the intervention radiologist is also suggestive of a safe procedure to be performed by maintaining the radiation dose well within the permissible limit for radiation professionals.

Radiation levels outside a patient undergoing177Lu-PSMA radioligand therapy

Understanding the spatial distribution of radiation levels outside of a patient undergoing177Lu radioligand therapy is not only helpful for conducting correct tests for patient release, but also useful for estimation of its potential exposure to healthcare workers, caregivers, family members, and the general public. In this study, by mimicking the177Lu-labeled prostate-specific membrane antigen radioligand therapy for prostate cancers in an adult male, the spatial distribution of radiation levels outside of the phantom was simulated based on the Monte Carlo software of Particle and Heavy Ion Transport System, and verified by a series of measurements. Moreover, the normalized dose rates were further formulized on the three transverse planes representing the heights of pelvis, abdomen and chest. The results showed that the distributions of radiation levels were quite complex. Multi-directional and multi-height measurements are needed to ensure the external dose rate to meet the release criteria. In general, the radiation level was higher at the horizontal plane where the source was located, and the levels in front and behind of the body were higher than those of the left and right sides at the same height. The ratio of simulated dose rates to measured ones ranged from 0.82 to 1.19 within 1 m away from the body surface in all directions. Based on the established functions, the relative root mean square deviation between the calculated and simulated values were 0.21, 0.25 and 0.23 within a radius of 1 m on the pelvis, abdomen and chest transverse planes, respectively. It is expected that the results of this study would be helpful for guiding the test of extracorporeal radiation to determine the patient's release, and of benefit to estimate the radiation exposure to others.

Dosing lutetium Lu 177-dotatate for a hemodialysis patient

Lu177-dotatate (Lutathera™) is a radioactive drug approved for the treatment of adults with gastro-entero-pancreatic neuroendocrine tumors and is predominantly renally excreted. Currently all patients receive 7400 MBq (200 mCi), and there are no guidelines for treating hemodialysis patients. We measured radioactivity prior to and post administration of two cycles of Lu177-dotatate in a hemodialysis patient, and radiation exposure to staff. We reduced the standard 7400 MBq by 33% for the first cycle and patient radioactivity fell by 40% following postdilution hemodiafiltration started 6 h post dosing, and by 45% for the second cycle and radioactivity fell by 47% with postdilution hemodiafiltration started 5 h post administration. By reducing the initial administered radioactivity, coupled with early dialysis, and choosing postdilution hemodiafiltration we were able to achieve radioactivity retention curves similar to those from patients with normal renal function receiving the standard administration of 7400 MBq.

Radiation exposure assessment of nuclear medicine staff administering [177Lu]Lu-DOTA-TATE with active and passive dosimetry

BACKGROUND

The use of lutetium-177 (177Lu)-based radiopharmaceuticals in peptide receptor nuclear therapy is increasing, but so is the number of nuclear medicine workers exposed to higher levels of radiation. In recent years, [177Lu]Lu-DOTA-TATE has begun to be widely used for the treatment of neuroendocrine tumours. However, there are few studies evaluating the occupational radiation exposure during its administration, and there are still some challenges that can result in higher doses to the staff, such as a lack of trained personnel or fully standardised procedures. In response, this study aims to provide a comprehensive analysis of occupational doses to the staff involved in the administration of [177Lu]Lu-DOTA-TATE.

RESULTS

A total of 32 administrations of [177Lu]Lu-DOTA-TATE (7.4 GBq/session) carried out by a physician and a nurse, were studied. In total, two physicians and four nurses were independently monitored with cumulative (passive) and/or real-time (active) dosemeters. Extremity, eye lens and whole-body doses were evaluated in terms of the dosimetric quantities Hp(0.07), Hp(3) and Hp(10), respectively. It was obtained that lead aprons reduced dose rates and whole-body doses by 71% and 69% for the physicians, respectively, and by 56% and 68% for the nurses. On average, normalised Hp(10) values of 0.65 ± 0.18 µSv/GBq were obtained with active dosimetry, which is generally consistent with passive dosemeters. For physicians, the median of the maximum normalised Hp(0.07) values was 41.5 µSv/GBq on the non-dominant hand and 45.2 µSv/GBq on the dominant hand. For nurses 15.4 µSv/GBq on the non-dominant and 13.9 µSv/GBq on the dominant hand. The ratio or correction factor between the maximum dose measured on the hand and the dose measured on the base of the middle/ring finger of the non-dominant hand resulted in a factor of 5/6 for the physicians and 3/4 for the nurses. Finally, maximum normalised Hp(3) doses resulted in 2.02 µSv/GBq for physicians and 1.76 µSv/GBq for nurses.

CONCLUSIONS

If appropriate safety measures are taken, the administration of [177Lu]Lu-DOTA-TATE is a safe procedure for workers. However, regular monitoring is recommended to ensure that the annual dose limits are not exceeded.

Effectiveness of shielding materials against 177Lu gamma rays and the corresponding distance relationship

OBJECTIVE

The purpose of this study is to determine the dose reduction of different shielding materials at various distances from a 177Lu photon radiation source.

METHODS

Two protective aprons with lead equivalent thicknesses of 0.25 mm and 0.35 mm and tungsten-containing rubber (TCR) were used as shielding materials. A vial containing 177Lu was sealed in a lead container so that a narrow beam went out through a 3 mm-diameter hole. The dose rate was measured at distances of 0, 10, 50, 100, and 200 cm from the source using a NaI scintillation survey meter to obtain the rate of dose reduction. TCR was tested with thicknesses ranging from 0.3 to 1.0 mm at 0.1 mm intervals and from 1.0 to 4.0 mm at 0.5 mm intervals.

RESULTS

At distances of 0, 10, 50, 100, and 200 cm, the dose reduction for the lead equivalent thickness of 0.25 mm were 32.7%, 54.5%, 93.1%, 97.9%, and 99.6%, respectively; and for the lead equivalent thickness of 0.35 mm were 53.4%, 70.6%, 95.6%, 98.9%, and 99.6%, respectively. Without any shielding, the dose rate decreased by 34.4% at 10 cm and by 88.8% at 50 cm from the radiation source. The dose reduction for the TCR thickness of 3.5 mm was 89.8% at 0 cm and 93.3% at 10 cm. The TCR thickness of 0.4 mm provided a dose reduction comparable to or greater than that of the 0.25 mm lead equivalent, whereas the TCR thickness of 1.0 mm or greater provided a dose reduction comparable to that of the 0.35 mm lead equivalent.

CONCLUSIONS

Achieving a reduction of 95% or more requires the 0.25 mm lead equivalent for a distance of 100 cm, the 0.35 mm lead equivalent for 50 cm, the TCR thickness of 0.3 mm for 100 cm, or the TCR thickness of 0.9 mm for 50 cm. Without wearing a protective apron, a reduction of approximately 95% is observed at distances greater than 100 cm. These findings would be useful for medical staff engaging in related activities.

Individualisation of radiation protection recommendations for patients treated with [177Lu]Lu-DOTA-TATE

BACKGROUND

As for any other nuclear medicine treatment, patients treated with [177Lu]Lu-DOTA-TATE should be given some radiation protection recommendations after being discharged to limit the dose received by family members and public. The restriction periods will depend on the remaining activity at the time of discharge, the washout rate and patients' personal conditions. The activity in patients' whole-body follows a bi-exponential behaviour. At the time of discharge only the first part of the time-activity curve is known. However, the second phase of the bi-exponential curve should be known to individualize the time of restrictions. The main purpose of this prospective study was to establish a simple method for calculating the restriction periods based on measurements taken before discharge.

METHODS

The whole-body time-activity curve was calculated for 20 patients from dose-rate measurements performed during the first week post-administration. An effective decay time [Formula: see text] was calculated from a mono-exponential fit performed with the 6 h and 24 h measurements and compared with the effective decay time [Formula: see text] obtained from the mono-exponential fit performed with the 24 h, 48 h and 168 h measurements. The differences between them were calculated and the 95th percentile of these differences was used as a correction factor for [Formula: see text]. A modified effective decay [Formula: see text] was obtained by adding the correction factor to [Formula: see text] and the restriction periods for each patient was calculated. The whole body activity washout between the first and the fourth treatment cycles of 16 patients was also compared.

RESULTS

The comparison of the whole-body activity curves between the first and the fourth cycle of the treatment for 16 patients would indicate that the recommendations on radiation protection determined from the first cycle could reasonably be used for the remaining cycles in most patients. The values of [Formula: see text] and [Formula: see text] obtained for the 20 patients were significantly different. The 95th percentile of the differences between [Formula: see text] and [Formula: see text] was 46 h, which is thus the time to be added to [Formula: see text] so as to determine the restriction periods.

CONCLUSIONS

The proposed method makes it possible to calculate the restriction periods for patients treated with [177Lu]Lu-DOTA-TATE before they leave the hospital in a conservative and individualized way.

Contact restriction time after common nuclear medicine therapies: spreadsheet implementation based on conservative retention function and individual measurements

The increasing use of new radiopharmaceuticals invites us to reconsider some radiation protection issues, such as the contact restriction time that limits public exposure by nuclear medicine patients. Contact restriction time should be patient specific and conservative, and its assessment made easy for clinicians. Here a method is proposed based on conservative estimation of the whole-body retention function and at least one measurement of the patient's dose rate. Recommended values of the retention function are given for eight therapies:¹³¹I (Graves' disease, remnant ablation, patient follow-up, meta-iodobenzylguanidine),¹⁷⁷Lu-prostate-specific membrane antigen and¹⁷⁷Lu-DOTATATE therapies, and⁹⁰Y and¹⁶⁶Ho microsphere injection of the liver. The patient line source model for scaling dose rate from one distance to another is included in the restriction time calculation. The method is benchmarked against published values and the influence of the dose rate scaling and whole-body retention function illustrated. A spreadsheet is provided, along with the source code, with recommended values for the eight therapies. The recommended values can be changed as well as the dose rate scaling function, and other radiopharmaceuticals can be included in the spreadsheet provided retention functions are defined.

Joint EANM, SNMMI, and IAEA Enabling Guide: How to Set up a Theranostics Center

The theranostics concept using the same target for both imaging and therapy dates back to the middle of the last century, when radioactive iodine was first used to treat thyroid diseases. Since then, radioiodine has become broadly established clinically for diagnostic imaging and therapy of benign and malignant thyroid disease, worldwide. However, only since the approval of SSTR2-targeting theranostics following the NETTER-1 trial in neuroendocrine tumors, and the positive outcome of the VISION trial has theranostics gained substantial attention beyond nuclear medicine. The roll-out of radioligand therapy for treating a high-incidence tumor such as prostate cancer requires the expansion of existing and the establishment of new theranostics centers. Despite wide global variation in the regulatory, financial and medical landscapes, this guide attempts to provide valuable information to enable interested stakeholders to safely initiate and operate theranostic centers. This enabling guide does not intend to answer all possible questions, but rather to serve as an overarching framework for multiple, more detailed future initiatives. It recognizes that there are regional differences in the specifics of regulation of radiation safety, but common elements of best practice valid globally.

SUBSTANTIAL EXTERNAL DOSE RATE VARIABILITY OBSERVED IN A COHORT OF LU-177 PATIENTS INDEPENDENT OF BMI AND SEX

External dose rates were measured 1 m away from 230 Lu-177 patients to characterise the variability in normalised dose rates as a function of administered activity, body mass index (BMI) and sex. The largest dose rate observed was 0.07 mSv/h associated with an administered activity of 7.2 GBq. Substantial variability was found in the distribution of the normalised dose rate associated that had an average of 0.0037 mSv/h per GBq and a 95% confidence interval of 0.0024-0.0058 mSv/h per GBq. Based on this study, estimating the patient dose rate based on the Lu-177 gamma exposure factor overestimates the dose rate by a factor of 2. A statistically significant inverse relationship was found between the patient dose rate and patient BMI and an empirically derived equation relating these two quantities was reported. On average, male patient dose rates were 3.5% lower than female dose rates, which may be attributed to the larger average BMI of the male patient group.

Radionuclides for Targeted Therapy: Physical Properties

A search in PubMed revealed that 72 radionuclides have been considered for molecular or functional targeted radionuclide therapy. As radionuclide therapies increase in number and variations, it is important to understand the role of the radionuclide and the various characteristics that can render it either useful or useless. This review focuses on the physical characteristics of radionuclides that are relevant for radionuclide therapy, such as linear energy transfer, relative biological effectiveness, range, half-life, imaging properties, and radiation protection considerations. All these properties vary considerably between radionuclides and can be optimised for specific targets. Properties that are advantageous for some applications can sometimes be drawbacks for others; for instance, radionuclides that enable easy imaging can introduce more radiation protection concerns than others. Similarly, a long radiation range is beneficial in targets with heterogeneous uptake, but it also increases the radiation dose to tissues surrounding the target, and, hence, a shorter range is likely more beneficial with homogeneous uptake. While one cannot select a collection of characteristics as each radionuclide comes with an unchangeable set, all the 72 radionuclides investigated for therapy-and many more that have not yet been investigated-provide numerous sets to choose between.

Joint EANM, SNMMI and IAEA enabling guide: how to set up a theranostics centre

The theranostics concept using the same target for both imaging and therapy dates back to the middle of the last century, when radioactive iodine was first used to treat thyroid diseases. Since then, radioiodine has become broadly established clinically for diagnostic imaging and therapy of benign and malignant thyroid disease, worldwide. However, only since the approval of SSTR2-targeting theranostics following the NETTER-1 trial in neuroendocrine tumours and the positive outcome of the VISION trial has theranostics gained substantial attention beyond nuclear medicine. The roll-out of radioligand therapy for treating a high-incidence tumour such as prostate cancer requires the expansion of existing and the establishment of new theranostics centres. Despite wide global variation in the regulatory, financial and medical landscapes, this guide attempts to provide valuable information to enable interested stakeholders to safely initiate and operate theranostics centres. This enabling guide does not intend to answer all possible questions, but rather to serve as an overarching framework for multiple, more detailed future initiatives. It recognizes that there are regional differences in the specifics of regulation of radiation safety, but common elements of best practice valid globally.

[Anticipating Criteria for Discharge after Lu-177-PSMA Treatment - Discussion of Several Scenarios]

AIM

The aim is to add a pragmatic contribution to the discussion of an algorithm to discharge patients treated with Lu-177-PSMA under the aspect of radiation protection. This also may be applied to therapies with other radioactive tracers in the future.

MATERIAL AND METHODS

478 cycles of Lu-177-PSMA-617 (140 patients) were analyzed. The remaining activity in the patient and the dose rate were correlated. From frequent intratherapeutic measurements (biexponential fit) scenarios for discharging patients are deduced.

RESULTS

Thirty-four per cent of all patients treated with Lu-177-PSMA received 3 to 5 cycles per calendar year. The dose limit of 1 mSv per calendar year (German Law) at a distance of 2 m from the patient would be exceeded in 10 % and 15 % of the treated patients if discharged 72 hours after treatment given 3 and 4 cycles per calendar year, respectively. Mean specific dose rate was 0.00462µSv/(h MBq) at a distance of 1 m. A universal correlation between dose rate and the remaining activity in the patient could not be found.

CONCLUSION

The multi cycle concept of the therapies with Lu-177 PSMA has to be taken into account prospectively when discharging the patients. Given the physical half-life of Lu-177 an anticipation of 4 treatment cycles per calendar year leads to a clearly arranged, conservative rule.

Radiation Safety and Accidental Radiation Exposures in Nuclear Medicine

Medical radiation accidents and unintended events may lead to accidental or unintended medical exposure of patients and exposure of staff or the public. Most unintended exposures in nuclear medicine will lead to a small increase in risk; nevertheless, these require investigation and a clinical and dosimetric assessment. Nuclear medicine staff are exposed to radiation emitted directly by radiopharmaceuticals and by patients after administration of radiopharmaceuticals. This is particularly relevant in PET, due to the penetrating 511 keV γ-rays. Dose constraints should be set for planning the exposure of individuals. Staff body doses of 1-25 µSv/GBq are reported for PET imaging, the largest component being from the injection. The preparation and administration of radiopharmaceuticals can lead to high doses to the hands, challenging dose limits for radionuclides such as ⁹⁰Y and even ¹⁸F. The risks of contamination can be minimized by basic precautions, such as carrying out manipulations in purpose-built facilities, wearing protective clothing, especially gloves, and removing contaminated gloves or any skin contamination as quickly as possible. Airborne contamination is a potential problem when handling radioisotopes of iodine or administering radioaerosols. Manipulating radiopharmaceuticals in laminar air flow cabinets, and appropriate premises ventilation are necessary to improve safety levels. Ensuring patient safety and minimizing the risk of incidents require efficient overall quality management. Critical aspects include: the booking process, particularly if qualified medical supervision is not present; administration of radiopharmaceuticals to patients, with the risk of misadministration or extravasation; management of patients' data and images by information technology systems, considering the possibility of misalignment between patient personal data and clinical information. Prevention of possible mistakes in patient identification or in the management of patients with similar names requires particular attention. Appropriate management of pregnant or breast-feeding patients is another important aspect of radiation safety. In radiopharmacy activities, strict quality assurance should be implemented at all operational levels, in addition to adherence to national and international regulations and guidelines. This includes not only administrative aspects, like checking the request/prescription, patient's data and the details of the requested procedure, but also quantitative tests according to national/international pharmacopoeias, and measuring the dispensed activity with a calibrated activity meter prior to administration. In therapy with radionuclides, skin tissue reactions can occur following extravasation, which can result in localized doses of tens of Grays. Other relevant incidents include confusion of products for patients administered at the same time or malfunction of administration devices. Furthermore, errors in internal radiation dosimetry calculations for treatment planning may lead to under or over-treatment. According to literature, proper instructions are fundamental to keep effective dose to caregivers and family members after patient discharge below the Dose constraints. The IAEA Basic Safety Standards require measures to minimize the likelihood of any unintended or accidental medical exposures and reporting any radiation incident. The relative complexity of nuclear medicine practice presents many possibilities for errors. It is therefore important that all activities are performed according to well established procedures, and that all actions are supported by regular quality assurance/QC procedures.

Preclinical dosimetric studies of 177 Lu-scFvD2B and comparison with 177 Lu-PSMA-617 and 177 Lu-iPSMA endoradiotherapeutic agents

PURPOSE

Internal dosimetry has become a very important tool to evaluate the risks and benefits of new endoradiotherapeutic agents. Nowadays, some of the most successful targeted radionuclide therapy (TRT) agents are ¹⁷⁷ Lu-DOTA conjugates based on low molecular weight (LMW) Glu-ureido PSMA inhibitors. It has, however, been demonstrated that the DOTA chelating moiety reduces the internalization of the LMW-PSMA agent and its radiation dose to the tumor. Previously, we reported that ¹⁷⁷ Lu-scFvD2B, an antibody-based construct, demonstrated statistically significant higher cell uptake and internalization in LNCaP prostate cancer (PCa) cells (PSMA-positive) when compared to the LMW-PSMA agents, ¹⁷⁷ Lu-PSMA-617 and ¹⁷⁷ Lu-iPSMA, two of the endoradiotherapeutic agents which currently are the most used in PCa therapy. The aim of this study is to estimate the preclinical ¹⁷⁷ Lu-scFvD2B organ and tumor-absorbed doses, and to compare the values with those of ¹⁷⁷ Lu-PSMA-617 and ¹⁷⁷ Lu-iPSMA.

METHODS

¹⁷⁷ Lu-scFvD2B, ¹⁷⁷ Lu-PSMA-617, and ¹⁷⁷ Lu-iPSMA were prepared and their radiochemical purity determined. Biodistribution studies of each radiopharmaceutical were then carried out in healthy mice to define the main source organs (SO) and to calculate the number of disintegrations in each source organs per unit of administered activity (N_SO ). Absorbed dose in the main organs were then calculated for each ¹⁷⁷ Lu-conjugate by means of OLINDA/EXM 2.1.1 software, using the calculated N_SO for both the adult male and the mouse phantoms as program inputs. Images of mice bearing micropulmonary tumors injected with ¹⁷⁷ Lu-conjugates were also obtained. Tumor standardized uptake values (SUV) for the different conjugates, obtained from the 3D SPECT image reconstruction of these mice, were used as the number of disintegrations in a tumor site per unit of administered activity (N_T ). The tumor-absorbed dose was calculated using the published electron dose S-values for sphere models with diameters ranging from 10 µm to 10 mm and considering a uniform activity distribution and tumor density equivalent to water density.

RESULTS

All ¹⁷⁷ Lu-labeled agents were obtained in high yield (98%). Dosimetric studies carried out using mouse phantoms demonstrated that organ absorbed doses of ¹⁷⁷ Lu-scFvD2B were from 1.4 to 2.3 times higher than those for ¹⁷⁷ Lu-iPSMA and from 1.5 to 2.6 times higher than those for ¹⁷⁷ Lu-PSMA-617. However, the ¹⁷⁷ Lu-scFvD2B values of tumor-absorbed doses for all investigated tumor sizes were from 2.8 to 3.0 times greater than those calculated for ¹⁷⁷ Lu-iPSMA and ¹⁷⁷ Lu-PSMA-617, respectively. Moreover, ¹⁷⁷ Lu-scFvD2B showed the highest tumor/kidney ratio when compared to those reported for ¹⁷⁷ Lu-albumin conjugates.

CONCLUSIONS

In this preclinical study, we demonstrated the potential of ¹⁷⁷ Lu-scFvD2B as a therapeutic agent for PSMA-expressing tumors, due to its higher tumor-absorbed dose when compared with ¹⁷⁷ Lu-LMW agents.

Patient external dose rate after 177Lu-DOTATATE therapy: factors affecting its decrease and predictive value

Rationale: Peptide receptor radionuclide therapy (PRRT) with 177Lu-DOTATATE (oxodotreotide) results in external radiation exposure from the patient. In the PREELU observational prospective study, we determined the equivalent dose rate at 1 m of the patient (EDR-1m) for a period following PRRT. The main objective was to predict which patients could be discharged from the hospital at approximately 3 h after the administration of 177Lu-DOTATATE, i.e. at the end of the infusion of amino-acids according to our PRRT protocol. As presenting no undue risk of radiation exposure for the public, those patients could be treated as outpatients or day patients, rather than inpatients. Methods: We sequentially measured EDR-1m facing the sternum and then the pelvis during 50 PRRT in 24 patients with metastatic neuroendocrine tumours, each 30 minutes after ending administration of Lutathera, over at least 180 minutes. Results: 180 minutes after the administration of ca. 7400 MBq of Lutathera, EDR-1m was <40 µSv/h in all cases, and <25 µSv/h in 32 cases (64%). After an overnight hospital stay, EDR-1m was <25 µSv/h in all cases. The EDR-1m value measured facing the sternum was the greatest in about one-fourth of paired measurements. In patients whose creatinine clearance was >96 mL/min/1.73m2, the EDR-1m was most likely (predictive value=90%) to drop below 25 µSv/h within 180 minutes after the administration of Lutathera. In 16 patients who benefited from several PRRT cycles, the creatinine clearance did not decrease significantly from one cycle to the next, probably due to the kidney protection by the amino-acid infusion. The patients whose EDR-1m dropped below 25 µSv/h at 180 minutes during their first PRRT cycle were unlikely (predictive value= 88%) to decease during the following two years. Conclusion: All patients could have been discharged 3 h after administration according to the criterion EDR-1m <40 µSv/h. Using EDR-1m <25 µSv/h as criterion, an extended hospital stay beyond 3 h would have been necessary in around one-third of the PRRT treatments and could be anticipated based on creatinine clearance ≤96 mL/min/1.73m2. EDR-1m <25 µSv/h at 180 min during the first PRRT yielded a strong predictive value on the patient's survival at two years, a finding that should be confirmed in future studies.

Imaging and dosimetric characteristics of 67 Cu

In recent years the use of beta-emitting radiopharmaceuticals for cancer therapy has expanded rapidly following development of therapeutics for neuroendocrine tumors, prostate cancer, and other oncologic malignancies. One emerging beta-emitting radioisotope of interest for therapy is ⁶⁷Cu (t_1/2: 2.6 d) due to its chemical equivalency with the widely-established positron-emitting isotope ⁶⁴Cu (t_1/2: 12.7 h). In this work we evaluate both the imaging and dosimetric characteristics of ⁶⁷Cu, as well as producing the first report of SPECT/CT imaging using ⁶⁷Cu. To this end, ⁶⁷Cu was produced by photon-induced reactions on isotopically-enriched ⁶⁸Zn at the Low-Energy Accelerator Facility (LEAF) of Argonne National Laboratory, followed by bulk separation of metallic ⁶⁸Zn by sublimation and radiochemical purification by column chromatography. Gamma spectrometry was performed by efficiency-calibrated high-purity germanium (HPGe) analysis to verify absolute activity calibration and establish radionuclidic purity. Absolute activity measurements corroborated manufacturer-recommended dose-calibrator settings and no radionuclidic impurities were observed. Using the Clinical Trials Network anthropomorphic chest phantom, SPECT/CT images were acquired. Medium energy (ME) SPECT collimation was found to provide the best image quality from the primary 185 keV gamma emission of ⁶⁷Cu. Reconstructed images of ⁶⁷Cu were similar in quality to images acquired using ¹⁷⁷Lu. Recovery coefficients were calculated and compared against quantitative images of ^99mTc, ¹⁷⁷Lu, and ⁶⁴Cu within the same anthropomorphic chest phantom. Production and clinical imaging of ⁶⁷Cu appears feasible, and future studies investigating the therapeutic efficacy of ⁶⁷Cu-based radiopharmaceuticals are warranted.

Advances in multimodal data fusion in neuroimaging: Overview, challenges, and novel orientation

Multimodal fusion in neuroimaging combines data from multiple imaging modalities to overcome the fundamental limitations of individual modalities. Neuroimaging fusion can achieve higher temporal and spatial resolution, enhance contrast, correct imaging distortions, and bridge physiological and cognitive information. In this study, we analyzed over 450 references from PubMed, Google Scholar, IEEE, ScienceDirect, Web of Science, and various sources published from 1978 to 2020. We provide a review that encompasses (1) an overview of current challenges in multimodal fusion (2) the current medical applications of fusion for specific neurological diseases, (3) strengths and limitations of available imaging modalities, (4) fundamental fusion rules, (5) fusion quality assessment methods, and (6) the applications of fusion for atlas-based segmentation and quantification. Overall, multimodal fusion shows significant benefits in clinical diagnosis and neuroscience research. Widespread education and further research amongst engineers, researchers and clinicians will benefit the field of multimodal neuroimaging.

One decade of 'Bench-to-Bedside' peptide receptor radionuclide therapy with indigenous [177Lu]Lu-DOTATATE obtained through 'Direct' neutron activation route: lessons learnt including practice evolution in an Indian setting

The present treatise chronicles one decade of experience pertaining to clinical PRRT services in a large-volume tertiary cancer care centre in India delivering over 4,000 therapies, an exemplar of successful PRRT programme employing indigenous 177Lutetium production and resources. For the purpose of systematic discussion, we have sub-divided the communication into 3 specific parts: (a) Radiopharmaceutical aspects that describes 177Lutetium production through 'Direct' Neutron Activation Route and the subsequent radiolabeling procedures, (b) The specific clinical nuances and finer learning points (apart from the routine standard procedure) based upon clinical experience and how it has undergone practice evolution in our setting and (c) Dosimetry results with this indigenous product and radiation safety/health physics aspects involved in PRRT services. Initiated in 2010 at our centre, the PRRT programme is a perfect example of affordable quality health care delivery, with indigenous production of the radionuclide (177Lu) in the reactor and subsequent radiolabeling of the radiopharmaceutical ([177Lu]Lu-DOTATATE) at the hospital radiopharmacy unit of the centre, which enabled catering to the needs of a large number of patients of progressive, metastatic and advanced Neuroendocrine Neoplasms (NENs) and related malignancies.

Initial experience and lessons learned with implementing Lutetium-177-dotatate radiopharmaceutical therapy in a radiation oncology-based program

PURPOSE

To assist radiation oncology centers in implementing Lutetium-177-dotatate (¹⁷⁷Lu) radiopharmaceutical therapy for midgut neuroendocrine tumors. Here we describe our workflow and how it was revised based on our initial experience on an expanded access protocol (EAP).

METHODS

A treatment team/area was identified. An IV-pump-based infusion technique was implemented. Exposure-based techniques were implemented to determine completion of administration, administered activity, and patient releasability. Acute toxicities were assessed at each fraction. A workflow failure modes and effects analysis (FMEA) was performed.

RESULTS

A total of 22 patients were treated: 11 patients during EAP (36 administrations) and 11 patients after EAP (44 administrations). Mean ¹⁷⁷Lu infusion time was 37 min (range 26-65 min). Mean administered activity was 97% (range 90-99%). Mean patient exposures at 1 m were 1.9 mR/h (range 1.0-4.1 mR/h) post-¹⁷⁷Lu and 0.9 mR/h (range 0.4-1.8 mR/h) at discharge, rendering patients releasable with instructions. Treatment area was decontaminated and released same day. All patients in the EAP experienced nausea, and nearly half experienced emesis despite premedication with antiemetics. Peripheral IV-line complications occurred in six treatments (16.7%), halting administration in 2 cases (5.6%). We transitioned to peripherally inserted central catheter (PICC)-lines and revised amino acid formulary after the EAP. The second cohort of 11 patients after EAP were analyzed for PICC-line complications and acute toxicity. Nausea and emesis rates decreased (nausea G1+ 61%-27%; emesis G1+ 23%-7%), and no PICC complications were observed. FMEA revealed that a failure in amino acid preparation was the highest risk.

CONCLUSION

¹⁷⁷Lu-dotatate can be administered safely in an outpatient radiation oncology department.

Patient Selection and Toxicities of PRRT for Metastatic Neuroendocrine Tumors and Research Opportunities

OPINION STATEMENT

Neuroendocrine tumors (NETs) are a heterogenous group of neoplasms characterized by varied biological hallmarks and behavior, ranging from indolent to aggressive. For many decades, somatostatin analogues and few targeted therapies were available for NETs and these therapies had minimal response rates. However, there have been a number of recent treatment advances. Peptide receptor radionuclide therapy (PRRT) is a novel approach to treatment of NETs and has changed the landscape of treatment for NETs. It is a form of targeted therapy in which a radiolabeled somatostatin analogue delivers radiation specifically to tumor cells expressing the somatostatin receptor.