Tracking the fate of bacteria-derived site-specific immunomodulators by positron emission tomography

INTRODUCTION

Site-specific immunomodulators (SSIs) are a novel class of therapeutics made from inactivated bacterial species designed to regulate the innate immune system in targeted organs. QBECO is a gut-targeted SSI that is being advanced clinically to treat and/or prevent inflammatory bowel disease, cancer, and serious infections of the gastrointestinal (GI) tract and proximal organs, and QBKPN is a lung-targeted SSI that is in clinical development for the treatment and/or prevention of chronic inflammatory lung disease, lung cancers and respiratory tract infections. While these SSIs have demonstrated both safety and proof-of-concept in preclinical and clinical studies, detailed understanding of their trafficking and biodistribution is yet to be fully characterized.

METHODS

QBECO and QBKPN were radiolabeled with [89Zr] and injected subcutaneously into healthy mice. The mice underwent Positron Emission Tomography (PET) imaging every day for eight days to track biodistribution of the SSIs. Tissue from the site of injection was collected and immunohistologically probed for immune cell infiltration.

RESULTS

Differential biodistribution of the two SSIs was seen, adhering to their site-specific targeting. QBKPN appeared to migrate from the site of injection (abdomen) to the cervical lymph nodes which are nearer to the respiratory tract and lungs. QBECO remained in the abdominal region, with lymphatic trafficking to the inguinal lymph nodes, which are nearer to GI-proximal tissues/organs. Immune infiltration at the site of injection comprised of neutrophils for both SSIs, and macrophages for only QBKPN.

CONCLUSION

Radiolabeling of SSIs allows for longitudinal in vivo imaging of biodistribution and trafficking. PET imaging revealed differential biodistribution of the SSIs based on the organotropism of the bacteria from which the SSI is derived. Trafficking from the site of injection to the targeted site is in part mediated via the lymphatics and involves macrophages and neutrophils.

In Vivo Tracking of Plasmid DNA/mRNA: a Novel Labelling Precursor for 89Zr Positron Emission Tomography

Herein, we developed a novel labelling precursor Fe-DFO-5 for plasmid DNA (pDNA) utilizing ⁸⁹Zr as a radioisotope for PET imaging. ⁸⁹Zr-labelled pDNA showed comparable gene expression to non-labelled pDNA. The biodistribution of ⁸⁹Zr-labelled pDNA after local or systemic administration in mice was evaluated. Furthermore, this labelling method was also applied to mRNA.

Radiation dosimetry and efficacy of an 89Zr/225Ac-labeled humanized anti-MUC5AC antibody

INTRODUCTION

Theranostic applications are currently difficult to achieve owing to the limited evaluation of suitable chelators for therapeutic nuclides, such as 225Ac and 227Th. With a focus on targeted α therapy and theranostics using human IgG as a drug-delivery system (i.e., combining highly cytotoxic α-particle emitter radiation with efficient tumor targeting), we developed a recombinant humanized Nd2 (hNd2) as an anti-MUC5AC antibody since MUC5AC is highly expressed in patients with pancreatic cancer. Therefore, we aimed to evaluate the performance of 89Zr- (for diagnosis) and 225Ac- (for therapy) labeling of these antibodies using well-controlled radioisotope (RI)-labeling technology in pancreatic cancer mouse models.

METHODS

89Zr-labeled hNd2 (NMK89) and 225Ac-labeled hNd2 (NMT25) were manufactured by chemical conjugation using affinity peptides. A binding assay and the evaluation of plasma stability were performed in vitro to confirm the properties of NMK89 and NMT25. In vivo, we evaluated biodistribution, positron emission tomography (PET)/computed tomography (CT) imaging, antitumor effects, and toxicity. Moreover, the exposure dose in humans was estimated based on the biodistribution evaluation in normal mice.

RESULTS

NMK89 and NMT25 showed binding specificity to MUC5AC and stability with radiochemical purity ≥90% in mice and human plasma following incubation for 168 h. NMK89 showed high accumulation in tumors and low non-specific accumulation in normal tissues. The antitumor effect of NMT25 was dose-dependent and significantly suppressed tumor growth in the NMT25 treatment groups compared with the control group (p < 0.05). NMK89 and NMT25 showed similar pharmacokinetics and biodistribution characteristics. Additionally, the human estimated exposure dose of NMK89 and NMT25 was confirmed, and the effective dose of NMK89 and NMT25 was 0.33 mSv/MBq and 177.5 mSv/MBq, respectively.

CONCLUSION

NMK89 showed specific accumulation in the MUC5AC-expressing tumors, while NMT25 showed strong antitumor effects. These results suggest NMK89 and NMT25 as promising theranostic agents for pancreatic cancer.

PET imaging of VEGFR and integrins in glioma tumor xenografts using 89Zr labelled heterodimeric peptide

Vascular endothelial growth factor receptor (VEGFR) and integrin αv are over-expressed in angiogenesis of variety malignant tumors with key roles in angiogenesis, and have been proven as valuable targets for cancer imaging and treatment. In this study, a heterodimeric peptide targeting VEGFR and integrin was designed, and radiolabeled with zirconium-89 (⁸⁹Zr) for PET imaging of glioma. ⁸⁹Zr-DFO-heterodimeric peptide, a the newly developed probe, was prepared with radiochemical yield of 88.7 ± 2.4%. Targeted binding capability of ⁸⁹Zr-DFO-heterodimeric peptide towards U87MG cells was investigated in murine glioma xenograft models, which shows that the designed probe has good binding ability to both targeting sites. Biodistribution indicated that kidney metabolism is the main pathway and tumor uptake of ⁸⁹Zr-DFO-heterodimeric peptide reached the peak of 0.62 ± 0.10% ID/g . U87MG xenograft could be clearly visualized by microPET/CT imaging through 1 to 3 h post-injection of ⁸⁹Zr-DFO-heterodimeric peptide. Importantly, the tumor radiouptake was significantly reduced after blocking, and the imaging effect of this radioactive compound was more obvious than that of monomeric peptide probes. ⁸⁹Zr-DFO-heterodimeric peptide has been demonstrated to show potential as a new radiopharmaceutical probe towards glioma, and multi-target probes do have advantages in tumor imaging.

Activity standardization by means of liquid scintillation counting and determination of the half-life of 89Zr

A⁸⁹Zr solution was measured by means of liquid scintillation counting techniques in order to determine the activity concentration. Two methods were used: the CIEMAT/NIST efficiency tracing method with ³H as a tracer, and the triple-to-double coincidence ratio method. The counting efficiencies were computed with a stochastic model. The very detailed investigation showed that a few corrections are particularly important: Asymmetries in the photodetector responses as well as the backscattering of high-energy gamma rays must be taken into account. Corresponding corrections have therefore been applied. In addition, a detailed uncertainty analysis was carried out and the uncertainties compared with those determined by other research groups. The activity concentrations obtained from the two methods agree well and a combined result was used to establish calibration factors for ionization chambers, which are important secondary standardization instruments. The ionization chambers were combined with a new high-precision current measurement device to provide outstanding linearity. Measurement data from one chamber were used to determine the half-life, which was found to be T_1/2=(78.373 ± 0.023) h.

89Zr-pembrolizumab imaging as a non-invasive approach to assess clinical response to PD-1 blockade in cancer

BACKGROUND

Programmed cell death protein-1 (PD-1) antibody treatment is standard of care for melanoma and non-small cell lung cancer (NSCLC). Accurately predicting which patients will benefit is currently not possible. Tumor uptake and biodistribution of the PD-1 antibody might play a role. Therefore, we performed a positron emission tomography (PET) imaging study with zirconium-89 (⁸⁹Zr) labeled pembrolizumab before PD-1 antibody treatment.

PATIENTS AND METHODS

Patients with advanced or metastatic melanoma or NSCLC received 37 MBq (1 mCi) ⁸⁹Zr-pembrolizumab (∼2.5 mg antibody) intravenously plus 2.5 or 7.5 mg unlabeled pembrolizumab. After that, up to 3 PET scans were performed on days 2, 4, and 7. Next, PD-1 antibody treatment was initiated. ⁸⁹Zr-pembrolizumab tumor uptake was calculated as maximum standardized uptake value (SUV_max) and expressed as geometric mean. Normal organ uptake was calculated as SUV_mean, and expressed as a mean. Tumor response was assessed according to (i)RECIST v1.1.

RESULTS

Eighteen patients, 11 with melanoma and seven with NSCLC, were included. The optimal dose was 5 mg pembrolizumab, and the optimal time-point for PET scanning was day 7. The tumor SUV_max did not differ between melanoma and NSCLC (4.9 and 6.5, P = 0.49). Tumor ⁸⁹Zr-pembrolizumab uptake correlated with tumor response (Ptrend = 0.014) and progression-free (P = 0.0025) and overall survival (P = 0.026). ⁸⁹Zr-pembrolizumab uptake at 5 mg was highest in the spleen with mean SUV_mean 5.8 (±SD 1.8). There was also ⁸⁹Zr-pembrolizumab uptake in Waldeyer's ring, normal lymph nodes, and at sites of inflammation.

CONCLUSION

⁸⁹Zr-pembrolizumab uptake in tumor lesions correlated with treatment response and patient survival. ⁸⁹Zr-pembrolizumab also showed uptake in lymphoid tissues and at sites of inflammation.

Assessment of absorbed dose for Zr-89, Sm-153 and Lu-177 medical radioisotopes: IDAC-Dose2.1 and OLINDA experience

OBJECTIVE

In this article, IDAC-Dose2.1 and OLINDA computer codes are compared as they are the most widely used software tools for internal dosimetry assessment at the present time. OLINDA/EXM personal computer code was created as a replacement for the widely used MIRDOSE3.1 code. IDAC-Dose2.1 was developed based on the ICRP specific absorbed fractions and computational framework of internal dose assessment given for reference adults in ICRP Publication 133. IDAC uses cumulated activities per administered activity in hours and calculates the absorbed dose and the effective dose. The program calculates the dose in the Eckerman stylized family phantoms. It is useful in standardizing and automating internal dose calculations, assessing doses in clinical trials with radiopharmaceuticals, making theoretic calculations for existing pharmaceuticals, teaching, and other purposes.

METHODS

To produce such a comparison, the results of this work were compared with available published data in the literature on radiopharmaceuticals. Radiopharmaceuticals with ⁸⁹Zr, ¹⁵³Sm, ¹⁷⁷Lu radionuclides are used as the basis for the comparison. ⁸⁹Zr, ¹⁵³Sm, ¹⁷⁷Lu radionuclides are regarded as the future of radiopharmaceutical treatment. For ⁸⁹Zr, two different labelled carriers, Zr-89_cMAb U36 and Zr-89 Panitumumab, were used on patients.

RESULTS

The results show a clear difference in terms of absorbed dose of the Zr-89 radiopharmaceuticals for red bone marrow when calculated by IDAC-Dose2.1 (0.76 mGy/MBq), while the estimated absorbed dose in literature results is 0.07 mGy/MBq and 0.14 mGy/MBq when the calculation is done by OLINDA program. In the case of ¹⁷⁷Lu-EDTMP, the absorbed dose in red bone marrow is in reasonable agreement (0.63 mGy/MBq and 0.8 mGy/MBq for IDAC-Dose2.1 and OLINDA, respectively). A significant difference was found for the absorbed dose in the bone surface, which was almost twice as high for OLINDA (2.1 mGy/MBq for IDAC-Dose2.1 and 5.4 mGy/MBq for OLINDA). In some direct cases, the calculated absorbed dose in the urinary bladder wall with OLINDA is ten times higher compared to WinAct (which was utilized to calculate the total activity in the organs and tissues) and IDAC 2.1. These results are considered key to greater accuracy in internal dose calculation.

A comparison of DFO and DFO* conjugated to trastuzumab-DM1 for complexing 89Zr - In vitro stability and in vivo microPET/CT imaging studies in NOD/SCID mice with HER2-positive SK-OV-3 human ovarian cancer xenografts

INTRODUCTION

Desferrioxamine (DFO) is conjugated to antibodies to chelate ⁸⁹Zr for PET, but DFO forms a hexadentate complex with Zr⁴⁺ that exhibits instability contributing to bone uptake of ⁸⁹Zr, while the cationic charge of the Zr⁴⁺-DFO complex may promote normal tissue uptake of the radioimmunoconjugates (RICs). DFO* is a novel chelator that forms a more stable octadentate and neutral complex with ⁸⁹Zr. Our aim was to compare the in vitro stability of [⁸⁹Zr]Zr-DFO*-human IgG (hIgG) and [⁸⁹Zr]Zr-DFO-hIgG RICs, and the in vivo PET imaging properties of the antibody-drug conjugate (ADC), trastuzumab-DM1 (T-DM1), labeled with ⁸⁹Zr by conjugation to DFO or DFO*.

METHODS

SCN-pPhe-DFO and SCN-pPhe-DFO* were reacted with hIgG at a 14.6-fold excess or with T-DM1 at a 4.1-fold or 10-fold excess, respectively, purified and labeled with ⁸⁹Zr. The number of DFO* introduced was determined by measuring the absorbance at 245/252 nm and the protein concentration was measured at 280 nm. The stability of [⁸⁹Zr]Zr-DFO*-hIgG was studied in vitro in human plasma, and by challenge with a 385-fold excess (0.1 mM) of DFO or EDTA. An inverse stability study was performed with [⁸⁹Zr]Zr-DFO-hIgG challenged with 0.1 mM DFO*. The HER2 binding affinity of [⁸⁹Zr]Zr-DFO*-T-DM1 was measured in a direct (saturation) binding assay using SK-BR-3 human breast cancer cells or SK-OV-3 human ovarian cancer cells. The biodistribution of [⁸⁹Zr]Zr-DFO*-T-DM1 and [⁸⁹Zr]Zr-DFO-T-DM1 were compared in non-tumor bearing Balb/c mice and in NOD/SCID mice with s.c. SK-OV-3 xenografts at 96 h post-intravenous injection (p.i.). MicroPET/CT images were obtained at 96 h p.i. of the RICs.

RESULTS

hIgG and T-DM1 were conjugated to 4.5-5.3 and 3.1 chelators (DFO or DFO*), respectively, and labeled with ⁸⁹Zr to a final radiochemical purity of 91-99%. [⁸⁹Zr]Zr-DFO*-hIgG was stable in vitro in human plasma or to challenge with 0.1 mM EDTA, but incubation with 0.1 mM DFO caused 26.0 ± 2.1% loss of ⁸⁹Zr after 5 days. In contrast, incubation of [⁸⁹Zr]Zr-DFO-hIgG with 0.1 mM DFO* resulted in 77.0 ± 3.9% loss of ⁸⁹Zr after 5 days. [⁸⁹Zr]Zr-DFO*-T-DM1 retained high affinity binding to HER2 on SK-BR-3 and SK-OV-3 cells with a K_d = 2.2 ± 0.3 nM and 1.9 ± 0.3 nM, respectively, and B_max = 3.4 ± 0.1 × 10⁵ and 1.1 ± 0.04 × 10⁵ receptors/cell, respectively. Biodistribution studies of [⁸⁹Zr]Zr-DFO-T-DM1 and [⁸⁹Zr]Zr-DFO*-T-DM1 in Balb/c and NOD/SCID mice revealed significantly lower uptake in bone, liver, kidneys, and spleen for [⁸⁹Zr]Zr-DFO*-T-DM1 than [⁸⁹Zr]Zr-DFO-T-DM1. Uptake of [⁸⁹Zr]Zr-DFO*-T-DM1 and [⁸⁹Zr]Zr-DFO-T-DM1 in SK-OV-3 tumors was moderate [5.0 ± 1.8% injected dose/g (%ID/g) and 6.3 ± 0.6%ID/g, respectively; P = 0.18]. Tumors were imaged with both RICs.

CONCLUSION

We conclude that DFO* conjugated to T-DM1 provides more stable complexation of ⁸⁹Zr and therefore, [⁸⁹Zr]Zr-DFO*-T-DM1 would be more useful than [⁸⁹Zr]Zr-DFO-T-DM1 to probe the delivery of T-DM1 to tumors by PET, which we previously found is correlated with response to treatment with T-DM1 in mouse tumor xenograft models.

ADVANCES IN KNOWLEDGE AND IMPLICATION FOR PATIENT CARE

This study is the first to directly compare the PET imaging properties of [⁸⁹Zr]Zr-DFO*-T-DM1 and [⁸⁹Zr]Zr-DFO-T-DM1 in a HER2-overexpressing tumor xenograft mouse model. Our results indicate that [⁸⁹Zr]Zr-DFO*-T-DM1 provides superior imaging properties due to the greater stability of the [⁸⁹Zr]Zr-DFO* than [⁸⁹Zr]Zr-DFO complex.

Tandem column isolation of zirconium-89 from cyclotron bombarded yttrium targets using an automated fluidic platform: Anion exchange to hydroxamate resin columns

The development of a tandem column purification method for the preparation of high-purity ⁸⁹Zr(IV) oxalate is presented. The primary column was a macroporous strongly basic anion exchange resin on styrene divinylbenzene co-polymer. The secondary column, with an internal volume of 33 μL, was packed with hydroxamate resin. A condition of inverted selectivity was developed, whereby the ⁸⁹Zr eluent solution for the primary column is equivalent to the ⁸⁹Zr load solution for the secondary column. The ability to transfer ⁸⁹Zr from one column to the next allows two sequential column clean-up methods to be performed prior to the final elution of the ⁸⁹Zr(IV) oxalate. This approach assures delivery of high purity ⁸⁹Zr product and assures a ⁸⁹Zr product that is eluted in a substantially smaller volume than is possible when using the traditionally-employed single hydroxamate resin column method. The tandem column purification process has been implemented into a prototype automated fluidic system. The system is configured with on-line gamma detection so column effluents can be monitored in near-real time. The automated method was tested using seven cyclotron bombarded Y foil targets. It was found that 95.1 ± 1.3% of the ⁸⁹Zr present in the foils was recovered in the secondary column elution fraction. Furthermore, elution peak analysis of several ⁸⁹Zr elution profile radiochromatograms made possible the determination of ⁸⁹Zr recovery as a function of volume; a ⁸⁹Zr product volume that contains 90% of the mean secondary column elution peak can be obtained in 0.29 ± 0.06 mL (representing 86 ± 5% of the ⁸⁹Zr activity in the target). This product volume represents a significant improvement in radionuclide product concentration over the predominant method used in the field. In addition to the reduced ⁸⁹Zr product elution volume, titrations of the ⁸⁹Zr product with deferoxamine mesylate salt across two preparatory methods resulted in mean effective specific activity (ESA) values of 279 and 340 T Bq·mmole^-1 and mean bindable metals concentrations ([M_B]) of 13.5 and 16.7 nmole·g^-1. These ESA and [M_B] values infer that the ⁸⁹Zr(IV) oxalate product resulting from this tandem column isolation method has the highest purity reported to date.

Functional Imaging Methods for Assessment of Minimal Residual Disease in Multiple Myeloma: Current Status and Novel ImmunoPET Based Methods

Imaging plays a key role in assessment of myeloma. Osteolytic bone lesions are optimally assessed using structural imaging, however the structural changes lag the functional changes in the disease. Functional imaging with fluoro deoxy glucose (FDG) positron emission tomography (PET) computerized tomography (CT) is useful in assessment of high-risk myeloma. FDG PET provides prognostic information and is helpful in monitoring response to therapy. However, it is nonspecific and may not be optimal in assessing treatment response to immunotherapeutic agents. Imaging with targeted agents may allow for better assessment of changes from therapy, that is based on the specific targeted mechanism. ImmunoPET imaging is a novel method to assess targeting of specific antigen by therapeutic antibodies. This review summarizes the role of functional imaging and development of novel immunoPET agents for assessment of treatment response and residual disease.

ImmunoPET imaging of tissue factor expression in pancreatic cancer with 89Zr-Df-ALT-836

Overexpression of tissue factor (TF) has been associated with increased tumor growth, tumor angiogenesis, and metastatic potential in many malignancies, including pancreatic cancer. Additionally, high TF expression was shown to strongly correlate with poor prognoses and decreased survival in pancreatic cancer patients. Herein, we exploited the potential targeting of TF for positron emission tomography (PET) imaging of pancreatic cancer. The TF-targeted tracer was developed through radiolabeling of the anti-human TF monoclonal antibody (ALT-836) with ⁸⁹Zr. The tracer was characterized by fluorescence microscopy and flow cytometry assays in BXPC-3 and PANC-1 cells, two pancreatic cancer cell lines with high and low TF expression levels, respectively. Non-invasive PET scans were acquired in tumor-bearing mice injected with ⁸⁹Zr-Df-ALT-836. Additionally, ex vivo biodistribution, blocking, and histological studies were performed to establish the affinity and specificity of ⁸⁹Zr-Df-ALT-836 for TF in vivo. ⁸⁹Zr-labeling of Df-ALT-836 was achieved in high yield and good specific activity. Flow cytometry and microscopy studies revealed no detectable difference in TF-binding affinity between ALT-836 and Df-ALT-836 in vitro. Longitudinal PET scans unveiled a lasting and prominent ⁸⁹Zr-Df-ALT-836 uptake in BXPC-3 tumors (peak at 31.5±6.0%ID/g at 48h post-injection; n=3), which was significantly abrogated (2.3±0.5%ID/g at 48h post-injection; n=3) when mice were pre-injected with a blocking dose (50mg/kg) of unlabeled ALT-836. Ex vivo biodistribution data confirmed the accuracy of the PET results, and histological analysis correlated high tumor uptake with in situ TF expression. Taken together, these results attest to the excellent affinity and TF-specificity of ⁸⁹Zr-Df-ALT-836. With elevated, persistent, and specific accumulation in TF-positive BXPC-3 tumors, PET imaging using ⁸⁹Zr-Df-ALT-836 promises to open new avenues for improving future diagnosis, stratification, and treatment response assessment in pancreatic cancer patients.

Concurrent spectrometry of annihilation radiation and characteristic gamma-rays for activity assessment of selected positron emitters

A method is described to determine the activity of non-pure positron emitters in a radionuclide production environment by assessing the 511keV annihilation radiation concurrently with selected γ-lines, using a single High-Purity Germanium (HPGe) detector. Liquid sources of ²²Na, ⁵²Fe, ^52mMn, ⁶¹Cu, ⁶⁴Cu, ⁶⁵Zn, ⁶⁶Ga, ⁶⁸Ga, ⁸²Rb, ⁸⁸Y, ⁸⁹Zr and ¹³²Cs were prepared specifically for this study. Acrylic absorbers surrounding the sources ensured that the emitted β⁺-particles could not escape and annihilate away from the source region. The absorber thickness was matched to the maximum β⁺ energy for each radionuclide. The effect on the 511keV detection efficiency by the non-homogeneous distribution of annihilation sites inside the source and absorber materials was investigated by means of Monte Carlo simulations. It was found that no self-absorption corrections other than those implicit to the detector calibration procedure needed to be applied. The medically important radionuclide, ⁶⁴Cu, is of particular interest as its strongest characteristic γ-ray has an intensity of less than 0.5%. In spite of the weakness of its emission intensity, the 1346keV γ-line is shown to be suitable for quantifying the ⁶⁴Cu production yield after chemical separation from the target matrix has been performed.

Utilization of GEANT to calculation of production yield for 89Zr by charge particles interaction on 89Y, natZr and natSr

The ⁸⁹Zr, is one of the radionuclide with near-ideal properties for PET due to its suitable half-life and decay properties. The cross-section of ⁸⁹Zr via ⁸⁹Y(p,n)⁸⁹Zr, ⁸⁹Y(d,2n)⁸⁹Zr, ^natSr(α,xn)⁸⁹Zr and ^natZr(p,pxn)⁸⁹Zr, were calculated by the TALYS-1.8 code to predict the optimum range of charge particle energy. The Monte Carlo code GEANT4 was used to simulate the formation of ⁸⁹Zr in the target body. The simulated ⁸⁹Zr yield was in good agreement with published experimental results in the optimum energy range. According to the calculations, the ⁸⁹Y(p,n)⁸⁹Zr was superior to the other reactions useful to medical application.

Spot-welding solid targets for high current cyclotron irradiation

Zirconium-89 finds broad application for use in positron emission tomography. Its cyclotron production has been limited by the heat transfer from yttrium targets at high beam currents. A spot welding technique allows a three-fold increase in beam current, without affecting ⁸⁹Zr quality. An yttrium foil, welded to a jet-cooled tantalum support base accommodates a 50µA proton beam degraded to 14MeV. The resulting activity yield of 48±4 MBq/(μA∙hr) now extends the outreach of ⁸⁹Zr for a broader distribution.

A simple and convenient method for production of 89Zr with high purity

A simple and convenient method for radiochemical separation ⁸⁹Zr with no harmful substance was explored. The separated ⁸⁹Zr was found to be [⁸⁹Zr]Zr-chloride, and the recovery of the radioactivity was 85%±3% with high radionuclidic purity (99.99%). The yields of ⁸⁹Zr via the reaction of (p, n) or (d, 2n) on Y target were also evaluated on CS-30 cyclotron, indicating the latter was more favorable for the production of ⁸⁹Zr with a yield of 58±4 MBq/μA·h.

Calibration setting numbers for dose calibrators for the PET isotopes (52)Mn, (64)Cu, (76)Br, (86)Y, (89)Zr, (124)I

For PET radionuclides, the radioactivity of a sample can be conveniently measured by a dose calibrator. These devices depend on a "calibration setting number", but many recommended settings from manuals were interpolated based on standard sources of other radionuclide(s). We conducted HPGe gamma-ray spectroscopy, resulting in a reference for determining settings in two types of vessels containing one of several PET radionuclides. Our results reiterate the notion that in-house, experimental calibrations are recommended for different radionuclides and vessels.

Imaging quality of (44)Sc in comparison with five other PET radionuclides using Derenzo phantoms and preclinical PET

PET is the favored nuclear imaging technique because of the high sensitivity and resolution it provides, as well as the possibility for quantification of accumulated radioactivity. (44)Sc (T1/2=3.97h, Eβ(+)=632keV) was recently proposed as a potentially interesting radionuclide for PET. The aim of this study was to investigate the image quality, which can be obtained with (44)Sc, and compare it with five other, frequently employed PET nuclides using Derenzo phantoms and a small-animal PET scanner. The radionuclides were produced at the medical cyclotron at CRS, ETH Zurich ((11)C, (18)F), at the Injector II research cyclotron at CRS, PSI ((64)Cu, (89)Zr, (44)Sc), as well as via a generator system ((68)Ga). Derenzo phantoms, containing solutions of each of these radionuclides, were scanned using a GE Healthcare eXplore VISTA small-animal PET scanner. The image resolution was determined for each nuclide by analysis of the intensity signal using the reconstructed PET data of a hole diameter of 1.3mm. The image quality of (44)Sc was compared to five frequently-used PET radionuclides. In agreement with the positron range, an increasing relative resolution was determined in the sequence of (68)Ga<(44)Sc<(89)Zr<(11)C<(64)Cu<(18)F. The performance of (44)Sc was in agreement with the theoretical expectations based on the energy of the emitted positrons.

Imaging of hepatocellular carcinoma patient-derived xenografts using ⁸⁹Zr-labeled anti-glypican-3 monoclonal antibody

Imaging probes for early detection of hepatocellular carcinoma (HCC) are highly desired to overcome current diagnostic limitations which lead to poor prognosis. The membrane protein glypican-3 (GPC3) is a potential molecular target for early HCC detection as it is over-expressed in >50% of HCCs, and is associated with early hepatocarcinogenesis. We synthesized the positron emission tomography (PET) probe (89)Zr-DFO-1G12 by bioconjugating and radiolabeling the anti-GPC3 monoclonal antibody (clone 1G12) with (89)Zr, and evaluated its tumor-targeting capacity. In vitro, (89)Zr-DFO-1G12 was specifically taken up into GPC3-positive HCC cells only, but not in the GPC3-negative prostate cancer cell line (PC3). In vivo, (89)Zr-DFO-1G12 specifically accumulated in subcutaneous GPC3-positive HCC xenografts only, but not in PC3 xenografts. Importantly, (89)Zr-DFO-1G12 delineated orthotopic HCC xenografts from surrounding normal liver, with tumor/liver (T/L) ratios of 6.65 ± 1.33 for HepG2, and 4.29 ± 0.52 for Hep3B xenografts. It also delineated orthotopic xenografts derived from three GPC3-positive HCC patient specimens, with T/L ratios of 4.21 ± 0.64, 2.78 ± 0.26, and 2.31 ± 0.38 at 168 h p.i. Thus, (89)Zr-DFO-1G12 is a highly translatable probe for the specific and high contrast imaging of GPC3-positive HCCs, which may aid early detection of HCC to allow timely intervention.

The production of radionuclides for nuclear medicine from a compact, low-energy accelerator system

INTRODUCTION

The field of nuclear medicine is reliant on radionuclides for medical imaging procedures and radioimmunotherapy (RIT). The recent shut-downs of key radionuclide producers have highlighted the fragility of the current radionuclide supply network, however. To ensure that nuclear medicine can continue to grow, adding new diagnostic and therapy options to healthcare, novel and reliable production methods are required. Siemens are developing a low-energy, high-current - up to 10 MeV and 1 mA respectively - accelerator. The capability of this low-cost, compact system for radionuclide production, for use in nuclear medicine procedures, has been considered.

METHODOLOGY

The production of three medically important radionuclides - (89)Zr, (64)Cu, and (103)Pd - has been considered, via the (89)Y(p,n), (64)Ni(p,n) and (103)Rh(p,n) reactions, respectively. Theoretical cross-sections were generated using TALYS and compared to experimental data available from EXFOR. Stopping power values generated by SRIM have been used, with the TALYS-generated excitation functions, to calculate potential yields and isotopic purity in different irradiation regimes.

RESULTS

The TALYS excitation functions were found to have a good agreement with the experimental data available from the EXFOR database. It was found that both (89)Zr and (64)Cu could be produced with high isotopic purity (over 99%), with activity yields suitable for medical diagnostics and therapy, at a proton energy of 10MeV. At 10MeV, the irradiation of (103)Rh produced appreciable quantities of (102)Pd, reducing the isotopic purity. A reduction in beam energy to 9.5MeV increased the radioisotopic purity to 99% with only a small reduction in activity yield.

CONCLUSION

This work demonstrates that the low-energy, compact accelerator system under development by Siemens would be capable of providing sufficient quantities of (89)Zr, (64)Cu, and (103)Pd for use in medical diagnostics and therapy. It is suggested that the system could be used to produce many other isotopes currently useful to nuclear medicine.

Production of 89Zr via the 89Y(p,n)89Zr reaction in aqueous solution: effect of solution composition on in-target chemistry

OBJECTIVE

The existing solid target production method of radiometals requires high capital and operational expenditures, which limit the production of radiometals to the small fraction of cyclotron facilities that are equipped with solid target systems. Our objective is to develop a robust solution target method, which can be applicable to a wide array of radiometals and would be simply and easily adopted by existing cyclotron facility for the routine production of radiometals.

METHOD

We have developed a simplified, solution target approach for production of (89)Zr using a niobium target by 14 MeV energy proton bombardment of aqueous solutions of yttrium salts via the (89)Y(p,n)(89)Zr nuclear reaction. The production conditions were optimized, following a detailed mechanistic study of the gas evolution.

RESULTS

Although the solution target approach avoided the expense and complication of solid target processing, rapid radiolytic formation of gases in the target represents a major impediment in the success of solution target. To address this challenge we performed a systematic mechanistic study of gas evolution. Gas evolution was found to be predominantly due to decomposition of water to molecular hydrogen and oxygen. The rate of gas evolutions varied >40-fold depending on solution composition even under the same irradiation condition. With chloride salts, the rate of gas evolution increased in the order rank Na<Ca<Y. However, the trend was reversed with the corresponding nitrate salts, and further addition of nitric acid to the irradiating solution minimized gas evolution. At optimized condition, (89)Zr was produced in moderate yield (4.36 ± 0.48 MBq/μA • h) and high effective specific activity (464 ± 215 MBq/μg) using the solution target approach (2.75 M yttrium nitrate, 1.5 N HNO3, 2h irradiation at 20 μA).

CONCLUSION

The novel findings on substrate dependent, radiation-induced water decomposition provide fundamental data for the development and optimization of conditions for solution targets. The developed methodology of irradiation of nitrate salts in dilute nitric acid solutions can be translated to the production of a wide array of radiometals like (64)Cu, (68)Ga and (86)Y, and is well suited for short-lived isotopes.

Mapping biological behaviors by application of longer-lived positron emitting radionuclides

With the technological development of positron emission tomography (PET) and the advent of novel antibody-directed drug delivery systems, longer-lived positron-emitting radionuclides are moving to the forefront to take important roles in tracking the distribution of biotherapeutics such as antibodies, and for monitoring biological processes and responses. Longer half-life radionuclides possess advantages of convenient on-site preparation procedures for both clinical and non-clinical applications. The suitability of the long half-life radionuclides for imaging intact monoclonal antibodies (mAbs) and their respective fragments, which have inherently long biological half-lives, has attracted increased interest in recent years. In this review, we provide a survey of the recent literature as it applies to the development of nine-selected longer-lived positron emitters with half-lives of 9-140h (e.g., (124)I, (64)Cu, (86)Y and (89)Zr), and describe the biological behaviors of radionuclide-labeled mAbs with respect to distribution and targeting characteristics, potential toxicities, biological applications, and clinical translation potentials.