Transport model predictions of 225Ac production cross sections via energetic p, d and α irradiation of 232Th targets.

Monte Carlo transport codes PHITS and MCNP6 were used to calculate the production cross sections of 225,227Ac, 227,229Th, 223,225Ra, and 229,230,231Pa via the bombardment of a232Th target with energetic protons, deuterons, and α-particles. The incident projectile energies ranged between 10 and 800 MeV/nucleon. When possible, the predicted production cross sections were compared with the available experimental data and other predictions. The degree of the codes' abilities to match the measured data provides a qualitative assessment of the codes' abilities to predict data from similar, but unmeasured, projectile/target systems. In addition, a comparison between calculated cross sections and data may provide insight into possible improvements in the physics models employed by those transport codes.

Quantitative encapsulation and retention of 227Th and decay daughters in core-shell lanthanum phosphate nanoparticles.

Targeted alpha therapy (TAT) offers great promise for treating recalcitrant tumors and micrometastatic cancers. One drawback of TAT is the potential damage to normal tissues and organs due to the relocation of decay daughters from the treatment site. The present study evaluates La(227Th)PO4 core (C) and core +2 shells (C2S) nanoparticles (NPs) as a delivery platform of 227Th to minimize systemic distribution of decay daughters, 223Ra and 211Pb. In vitro retention of decay daughters within La(227Th)PO4 C NPs was influenced by the concentration of reagents used during synthesis, in which the leakage of 223Ra was between 0.4 ± 0.2% and 20.3 ± 1.1% in deionized water. Deposition of two nonradioactive LaPO4 shells onto La(227Th)PO4 C NPs increased the retention of decay daughters to >99.75%. The toxicity of the nonradioactive LaPO4 C and C2S NP delivery platforms was examined in a mammalian breast cancer cell line, BT-474. No significant decrease in cell viability was observed for a monolayer of BT-474 cells for NP concentrations below 233.9 µg mL-1, however cell viability decreased below 60% when BT-474 spheroids were incubated with either LaPO4 C or C2S NPs at concentrations exceeding 29.2 µg mL-1. La(227Th)PO4 C2S NPs exhibit a high encapsulation and in vitro retention of radionuclides with limited contribution to cellular cytotoxicity for TAT applications.

Multifunctional GdVO4:Eu core-shell nanoparticles containing 225Ac for targeted alpha therapy and molecular imaging.

Gadolinium vanadate nanoparticles (NPs) doped with europium, in concentrations between 5-40%, were synthesized via an aqueous route to prove their multimodal imaging functionalities and their performance as radionuclide carriers for targeted alpha therapy. Core-shell Gd0.8Eu0.2VO4 NPs were doped with the α-emitting actinium-225 to assess the in vitro retention of 225Ac and its decay daughters; francium-221 and bismuth-213. Gd0.8Eu0.2VO4 core-shell NPs were obtained using a precipitation synthesis route having a tetragonal system, a spherical morphology, and a uniform particle size distribution. Gd0.8Eu0.2VO4 core-shell NPs displayed the characteristic intense emission at 618 nm (red) and paramagnetic behavior of Eu and Gd cations, respectively. Partial retention of radionuclides was obtained with Gd0.8Eu0.2VO4 core NPs, while deposition of two nonradioactive Gd0.8Eu0.2VO4 shells significantly decreased the leakage of both 225Ac and 221Fr. The luminescence and magnetic functionalities as well as radionuclide retention capabilities of Gd0.8Eu0.2VO4 core-shell NPs demonstrate their potential for biomedical applications.

Large scale accelerator production of 225Ac: Effective cross sections for 78-192MeV protons incident on 232Th targets.

Actinium-225 and 213Bi have been used successfully in targeted alpha therapy (TAT) in preclinical and clinical research. This paper is a continuation of research activities aiming to expand the availability of 225Ac. The high-energy proton spallation reaction on natural thorium metal targets has been utilized to produce millicurie quantities of 225Ac. The results of sixteen irradiation experiments of thorium metal at beam energies between 78 and 192MeV are summarized in this work. Irradiations have been conducted at Brookhaven National Laboratory (BNL) and Los Alamos National Laboratory (LANL), while target dissolution and processing was carried out at Oak Ridge National Laboratory (ORNL). Excitation functions for actinium and thorium isotopes, as well as for some of the fission products, are presented. The cross sections for production of 225Ac range from 3.6 to 16.7mb in the incident proton energy range of 78-192MeV. Based on these data, production of curie quantities of 225Ac is possible by irradiating a 5.0gcm-2 232Th target for 10 days in either BNL or LANL proton irradiation facilities.

Synthesis and characterization of lanthanum phosphate nanoparticles as carriers for (223)Ra and (225)Ra for targeted alpha therapy.

INTRODUCTION: Targeted alpha therapy (TAT) has the potential for killing micro-metastases with minimum collateral damage to surrounding healthy tissue. In-vivo generator radionuclides, such as(223)Ra, (225)Ra, and (225)Ac, are of special interest for radiotherapeutic applications as they emit multiple α-particles during their decay. Utilizing appropriate carriers capable of retaining both the parent radioisotope as well as daughter products is important for the effective delivery of the radioisotope to the tumor site while mitigating global in vivo radiotoxicity. In this work, LaPO4 core and core+2 shells nanoparticles (NPs) (NPs with 2 layers of cold LaPO4 deposited on the core surfaces) were synthesized containing either (223)Ra or(225)Ra/(225)Ac, and the retention of the parents and daughters within the NPs in vitro was investigated. METHODS: Core LaPO4 NPs were synthesized in aqueous solution by reacting 1 equivalent of La(NO3)3, along with few microcuries of either (223)Ra or (225)Ra/(225)Ac, with 1 equivalent of sodium tripolyphosphate (TPP) under moderate heating and purified by membrane dialysis. Core-shell NPs were also synthesized with one (core+1 shell) and two (core+2 shells) cold LaPO4 layers deposited onto the radioactive cores. The NPs were then characterized by transmission electron microscopy (TEM) and powder x-ray diffraction (XRD). Identification and quantification of radioactive parents and daughters released from the NPs in vitro were investigated using gamma-ray spectroscopy. RESULTS: XRD and TEM analysis revealed that the NPs crystallized in the rhabdophane phase with mean diameters of 3.4 and 6.3nm for core and core+2 shells, respectively. The core LaPO4 NPs retained up to 88% of (223)Ra over 35days. However, in the core+2 shells NPs, the retention of (223)Ra and its daughter, (211)Pb, was improved to >99.9% over 27days. Additionally, the retention of (225)Ra/(225)Ac parents was >99.98% and ~80% for the (221)Fr and (213)Bi daughters over 35days for the core+2 shells NPs. CONCLUSIONS: The in vitro retention of both parents and daughters results suggests that LaPO4 NPs are potentially effective carriers of radium isotopes.

Production of Sn-117m in the BR2 high-flux reactor.

The BR2 reactor is a 100MW(th) high-flux 'materials testing reactor', which produces a wide range of radioisotopes for various applications in nuclear medicine and industry. Tin-117m ((117m)Sn), a promising radionuclide for therapeutic applications, and its production have been validated in the BR2 reactor. In contrast to therapeutic beta emitters, (117m)Sn decays via isomeric transition with the emission of monoenergetic conversion electrons which are effective for metastatic bone pain palliation and radiosynovectomy with lesser damage to the bone marrow and the healthy tissues. Furthermore, the emitted gamma photons are ideal for imaging and dosimetry.

Neutron flux characterization of a peripheral target position in the High Flux Isotope Reactor.

The High Flux Isotope Reactor at the Oak Ridge National Laboratory provides the highest steady-state thermal neutron flux in the western world for a wide range of experiments and for isotope production. The highest available fluxes are located in a flux trap region created inside the nested fuel elements. The experimentally determined thermal and the empirically obtained epithermal flux values along the vertical axis of the peripheral target position were fit to cosine curves, with the thermal flux ranging from 1.1 x 10(15)ns(-1)cm(-2) at outer positions to 1.5 x 10(15)ns(-1)cm(-2) at the center. The corresponding epithermal flux ranged from 3.5 x 10(13) to 7.5 x 10(13)ns(-1)cm(-2), respectively. The fast neutron flux (En > or = 0.32 MeV in two positions and En > or = 1.5 MeV in two other positions) was approximately 6 x 10(14)ns(-1)cm(-2), corresponding to a fast to thermal ratio of approximately 0.4.

Decay of tungsten-189.

We studied the decay of 189W as produced via the 192Os[n,alpha]189W reaction on a 99.9% isotopically enriched 192Os target. The irradiations were performed at the intense neutron beam facility at Cyclotron Research Center, Université Catholique Louvain-la-Neuve (CRC-UCL) (Belgium), where fast neutrons [En approximately 20 MeV, phi(n) = (4.8 +/- 0.3)10(11) ns(-1) cm(-2)] were generated by stopping 50 MeV deuterons on a thick Be target. The half-life of 189W was determined to be 9.3 +/- 0.3min, compared to 10.8 +/- 0.2min obtained from the 188W[n,gamma]189W reaction. The energies of the two predominant gamma-rays of 189W, 260.4 +/- 1.3 and 421.7 +/- 1.4 keV were in good agreement with that from the [n,gamma] reaction, however, the relative intensities of the two gamma-rays were not consistent. From the [n,gamma] reaction, the relative intensities of the 260 and 421 keV gamma-rays were 97 to 100, whereas from the [n,alpha] reaction the relative intensities were 100 to 77, respectively. Assuming a cross-section ratio of 20 +/- 5 for [n,p3n] to [n,alpha] reactions, a cross-section of 0.5 +/- 0.2 mb was suggested for the 192Os[n,alpha]189W reaction, and the absolute intensity of the 260 keV gamma-ray was estimated to be approximately 50%.

Therapy of rat tracheal carcinoma IC-12 in SCID mice: vascular targeting with [213Bi]-MAb TES-23.

In previous work, we have demonstrated that vascular targeting of [213Bi], an alpha-emitter, to lung blood vessels could efficiently destroy tumour colonies growing in the lung. In order to expand this approach to treatment of tumours growing in other sites, we employed the monoclonal antibody (MAb) TES-23, which reacts with CD44H, preferentially expressed on new blood vessels in tumours. Biodistribution studies of N-succinimidyl [125I] 3-iodobenzoate (SIB)-radiolabelled MAb TES-23 in ICR-severe combined immunodeficient (SCID) mice bearing subcutaneous (s.c.) and intramuscular (i.m.) IC-12 tumours, demonstrated efficient tumour uptake. At 24 h, accumulation in small tumours was 45%ID/g for s.c. tumours, and 58%ID/g for i.m. tumours and in large tumours it was 25%ID/g for s.c. tumours and 17%ID/g for i.m. tumours. Micro-autoradiography data confirmed that radiolabel accumulated in or near tumour blood vessels. Normal tissues had very low levels of radioactivity. Treatment of mice bearing small IC-12 tumours with [213Bi] MAb TES-23 retarded tumour growth relative to animals treated with cold MAb TES-23. Biodistribution and therapy experiments were also performed in BALB/c mice bearing both s.c. and i.m. syngeneic, lung carcinoma (line 498) tumours. [I(125)] SIB MAb TES-23 accumulated efficiently in both s.c. and i.m. tumours (14%ID/g and 15%ID/g, respectively, at 4 h); however, no therapeutic effect of [213Bi] MAb TES-23 treatment could be demonstrated in this model system. The data demonstrate that the timing of vascularisation of the tumours and the delivery kinetics of MAb relative to the half-life of the therapeutic radionuclide are critical for effective therapy.

Vascular-targeted radioimmunotherapy with the alpha-particle emitter 211At.

Astatine-211, an alpha-particle emitter, was employed in a model system for vascular-targeted radioimmunotherapy of small tumors in mouse lung to compare its performance relative to other radioisotopes in the same system. Astatine-211 was coupled to the lung blood vessel-targeting monoclonal antibody 201B with N-succinimidyl N-(4-[211At]astatophenethyl) succinamate linker. Biodistribution data showed that the conjugate delivered 211At to the lung (260-418% ID/g), where it remained with a biological half-time of about 30 h. BALB/c mice bearing about 100 lung tumor colonies of EMT-6 cells, each about 2000 cells in size, were treated with 211At-labeled monoclonal antibody 201B. The administered activity of 185 kBq per animal extended the life span of treated mice over untreated controls. Injections of 370 kBq, corresponding to an absorbed dose of 25-40 Gy, were necessary to eradicate all of the lung tumors. Mice receiving 740 kBq of 211At-labeled monoclonal antibody 201B developed pulmonary fibrosis 3-4 months after treatment, as did mice treated with 3700 kBq of the alpha-particle emitter 213Bi-labeled monoclonal antibody 201B in previous work. Animals that were injected with 211At bound to untargeted IgG or to glycine, as control agents, also demonstrated therapeutic effects relative to untreated controls. Control groups that received untargeted 211At required about twice as much administered activity for effective therapy as did groups with lung-targeted radioisotope. These results were not consistent with radioisotope biodistribution and dosimetry calculations that indicated that lung-targeted 211At should be at least 10-fold more efficient for lung colony therapy than 211At bound to nontargeting controls. The data showed that 211At is useful for vascular-targeted radioimmunotherapy because lung tumor colonies were eradicated in the mice. Work in this model system demonstrates that vascular targeting of alpha-particle emitters is an efficient therapy for small perivascular tumors and may be applicable to human disease when specific targeting agents are identified.

In vivo evaluation of bismuth-labeled monoclonal antibody comparing DTPA-derived bifunctional chelates.

Among the radionuclides considered for radioimmunotherapy, alpha-emitters such as the bismuth isotopes, 212Bi and 213Bi, are of particular interest. The macrocyclic ligand, DOTA, has been shown to form stable complexes with bismuth isotopes. The kinetics of the complexation of bismuth with the DOTA chelate, however, are slow and impractical for use with 212Bi and 213Bi that have half-lives of 60.6 and 45.6 min. The study described herein compares six DTPA derived bifunctional chelates with the goal of identifying an alternative to the DOTA ligand for radiolabeling with bismuth. Radioimmunoconjugates comprised of MAb B72.3, each of the six DTPA chelates, and radiolabeled with 206Bi, which facilitated the evaluation due to its readily detectable gamma-emission. In vitro studies showed that each of the radioimmunoconjugates retained immunoreactivity that was comparable to its 125I-labeled counterpart. The 206Bi- and 125I-labeled immunoconjugates were then co-injected i.p. into normal athymic mice. Injection of Afree@ 206Bi demonstrated that the kidneys were the critical organ to evaluate for retention of bismuth in the chelate complex. Major differences were identified among the six preparations. The CHX-A and -B immunoconjugates were found to have 1) the lowest %ID/gm in the kidney; 2) a level of 206Bi in the kidney that was comparable to that of 125I-B72.3; and 3) no significant uptake of 206Bi evident in other organs such as bone, lung and spleen. The results described herein suggest that either of the cyclohexyl derivatives of DTPA may be suitable candidates for the labeling of immunoconjugates with alpha-emitting bismuth isotopes for radioimmunotherapeutic applications.

Evaluation of 225Ac for vascular targeted radioimmunotherapy of lung tumors.

Several alpha particle emitting radioisotopes have been studied for use in radioimmunotherapy. Ac-225 has the potential advantages of a relatively long half life of 10 days, and a yield of 4 alpha emissions in its decay chain with a total energy release of approximately 28 MeV. A new, 12 coordination site chelating ligand, HEHA, has been chemically modified for coupling to targeting proteins without loss of chelating ability. HEHA was coupled with MAb 201B which binds to thrombomodulin and accumulates efficiently in murine lung. Ac-225 was bound to the HEHA-MAb 201B conjugate and injected into BALB/c mice bearing lung tumor colonies of EMT-6 mammary carcinoma. Biodistribution data at 1 and 4 h postinjection indicated that, as expected, 225Ac was delivered to lung efficiently (> 300% ID/g). The 225Ac was slowly released from the lung with an initial t1/2 = 49 h, and the released 225Ac accumulated in the liver. Injection of free HEHA was only partially successful in scavenging free 225Ac. In addition to the slow release of 225Ac from the chelate, data indicated that decay daughters of 225Ac were also released from the lung. Immediately after organ harvest, the level of 213Bi, the third alpha-decay daughter, was found to be deficient in the lungs and to be in excess in the kidney, relative to equilibrium values. Injected doses of 225Ac MAb 201B of 1.0 microCi, delivering a minimum calculated absorbed dose of about 6 Gy to the lungs, was effective in killing lung tumors, but also proved acutely radiotoxic. Animals treated with 1.0 microCi or more of the 225Ac radioconjugate died of a wasting syndrome within days with a dose dependent relationship. We conclude that the potential for 225Ac as a radioimmunotherapeutic agent is compromised not only by the slow release of 225Ac from the HEHA chelator, but most importantly by the radiotoxicity associated with decay daughter radioisotopes released from the target organ.

Simple new method for effective concentration of 188Re solutions from alumina-based 188W-188Re generator.

UNLABELLED: (188)Re is a useful generator-produced radioisotope currently under evaluation for a variety of therapeutic applications, including bone pain palliation and intravascular radiation therapy. Because the (188)W parent is available only in a relatively low specific activity (<0.15-0.19 GBq/mg) from reactor irradiation of enriched (186)W, relatively large volumes of 0.9% saline (>15 mL) are required for elution of the (188)Re daughter from traditional alumina-based (188)W-(188)Re generators. Because these large bolus volumes result in solutions with a relatively low specific volume activity of (188)Re (<1 GBq/mL for the 18.5-GBq generator), the availability of effective methods for eluent concentration is important. Our new approach is based on the use of 0.3 mol/L ammonium acetate as a representative salt of a weak acid instead of saline for generator elution. METHODS: After generator elution, the ammonium acetate generator eluent (15-20 mL) is passed through a tandem IC-H Plus cation (Dowex-H)-anion (QMA Light) column system. Exchange of ammonium cations with hydrogen ions on the cation column forms an acetic acid solution containing perrhenate anions from which the macroscopic levels of the acetate anion of the eluent have been effectively removed. Because perrhenic acid is fully dissociated at this pH, the QMA Light column specifically traps the (188)Re-perrhenate, which is subsequently eluted with a low volume (<1 mL) of saline. Concentration ratios greater than 20:1 are readily achieved with this method. RESULTS: A typical clinical-scale generator loaded with 19.2 GBq (188)W was used to validate the approach. Saline elution provided (188)Re in a 75%-80% yield. Although elution with 0.15 mol/L NH4OAc gave lower yields (55%-60%), use of 0.3 mol/L NH4OAc provided yields comparable with those of saline (70%-75%). (188)W parent breakthrough was not detected after passage of the bolus through the tandem concentration system. Bolus volumes of 15-20 mL, which initially contained as much as 11.1-14.8 GBq (188)Re, were readily concentrated to less than 1 mL saline using QMA Light cartridges. The generator was evaluated for more than 3 mo with no decrease in performance. CONCLUSION: This approach represents a simple, rapid, and effective method using inexpensive disposable components of concentrating solutions of (188)Re for preparation of therapeutic agents.

Labeling and distribution of linear peptides identified using in vivo phage display selection for tumors.

To develop targeting molecules to be used for vascular targeting of short half-lived alpha-emitters for radioimmunotherapy, linear peptide phage display libraries were selected in vivo for binding to IC-12 rat tracheal tumors growing in severe combined immune deficient mice. After three rounds of selection, 15 phage clones were analyzed for DNA sequence, and the deduced translation products of cDNA inserts were compared. Three consensus sequences were chosen from three separate experimental selection series and peptides of these sequences with added -gly-gly-tyr were obtained. Peptides were radiolabeled on tyrosine with (125)I and the biodistribution in tumor-bearing mice was determined. The radioiodinated peptides were stable in vitro and when injected in tumor-bearing mice approximately 3.0 %ID/g accumulated in the tumor; however, much of the (125)I was found in the gastrointestinal tract and thyroid, indicative of dehalogenation of the labeled peptide. Radiolabeling peptide 2 with N-succinimidyl-3-(125)I-iodobenzoate resulted in faster excretion, which in turn resulted in lower levels in tumor and other organs, especially thyroid and gastrointestinal tract. Peptide 2 was derivatized with the bifunctional isothiocyanates of cyclohexyl-B diethylenetriaminepentaacetic acid (DTPA) or CHX-A" DTPA by direct conjugation or with a hydroxylamine derivative of 1B4M-DTPA (2-(p-[O-(carboxamylmethyl)hydroxylamine]benzyl)-6-methyl-diethylenetriamine-N,N,N',N",N"-pentaacetic acid ) coupled at the N-terminus. The primary molecular species in the conjugated products were shown by mass spectrometry to have one DTPA per peptide. Peptide chelate conjugates were radiolabeled with (213)Bi and the products tested for biodistribution in tumor-bearing mice. The data show that chelation of (213)Bi to peptides was accomplished by both the direct method of DTPA attachment and by the method using the linker at the N-terminus. Only small amounts of peptide accumulated at tumor sites. We conclude that phage display is a powerful tool to select peptides with restricted binding specificity; however, the peptides isolated to date do not bind with high retention to tumor sites in vivo.

Comparison of 225actinium chelates: tissue distribution and radiotoxicity.

The biodistribution and tissue toxicity of intravenously administered 225-actinium (225Ac) complexed with acetate, ethylene diamine tetraacetic acid (EDTA), 1, 4, 7, 10, 13-pentaazacyclopentadecane-N, N', N", N"', N""-pentaacetic acid (PEPA), or the "a" isomer of cyclohexyl diethylenetriamine pentaacetic acid (CHX-DTPA), were examined. The percent of injected dose per organ and per gram of tissue for each chelate complex was determined. 225Ac-CHX-DTPA was evaluated further for radiotoxic effects. Mice receiving > or =185 kBq 225Ac-CHX-DTPA suffered 100% morbidity by 5 days and 100% mortality by 8 days postinjection, and all animals evaluated had significant organ damage. The in vivo instability of the 225Ac-CHX-DTPA complex likely allowed accumulation of free 225Ac in organs, which resulted in tissue pathology.

Improved in vivo stability of actinium-225 macrocyclic complexes.

The favorable nuclear properties of actinium-225 ((225)Ac) have led to proposal of this isotope for use in radioimmunotherapy. In an effort to reduce the toxicity of free (225)Ac, a series of ligands were evaluated for stability in vivo. Loss of (225)Ac from acyclic chelating agents resulted in high liver uptake and poor whole body clearance. The macrocyclic ligands c-DOTA, PEPA, and HEHA were evaluated, and (225)Ac-HEHA showed exceptional stability in vivo. (225)Ac chelated with EDTA, DTPA, DOTA, or PEPA permitted substantial accumulation of the radionuclide to the liver, while the (225)Ac-HEHA complex was essentially excreted within minutes of administration. The preparation of the ligands and radiolabeled complexes and the biodistribution results will be discussed.

Radioimmunotherapy of micrometastases in lung with vascular targeted 213Bi.

A model system has been used to test the efficacy of vascular targeting of alpha-particle emitter 213Bi for therapy of small, 'artificial' metastases in mouse lung. Specific monoclonal antibody (mAb) 201 B was used to deliver greater than 30% of the injected dose to lung where tumours had developed due to intravenous injection of cells. Specific 213Bi-mAb 201B treatment of BALB/c mammary carcinoma EMT-6 tumours in lung resulted in a dose-dependent destruction of tumours and an extended lifespan of treated animals relative to controls. Significant reduction of lung tumour burden was noted in animals treated with 0.93 MBq injected dose or as little as 14 Gy absorbed dose to the lung. Animals treated with higher doses (2.6-6.7 MBq) had nearly complete cure of lung tumours but eventually died of lung fibrosis induced by the treatment. Four other tumour cell types were studied: murine Line 1 lung carcinomas in syngeneic BALB/c mice, rat IC-12 tracheal carcinoma growing in severe combined immune deficient (SCID) mice, and two human tumours--epidermoid carcinoma A431 and lung carcinoma A549--growing in SCID mice. In all cases, the number of lung tumour colonies was reduced in animals treated with specific, labelled mAb relative to those in animals treated with control 213Bi MAb or EDTA complexed 213Bi. Tumours treated in immunodeficient SCID mice were partially destroyed or at least retarded in growth, but ultimately regrew and proved fatal, indicating that an intact immune function is necessary for complete cure. The data show that the short-lived alpha-particle emitter 213Bi can be effectively targeted to lung blood vessels and that tumour cells growing in the lung are killed. The mechanism may involve direct killing of tumour cells from alpha-particle irradiation, killing through destruction of blood supply to the tumour, or a combination of the two.

In vivo studies of fullerene-based materials using endohedral metallofullerene radiotracers.

Biodistribution studies of a water-soluble radioactive metallofullerene compound have been conducted using BALB/c mice. To this end, a sample containing Hox@C82 (x = 1, 2) was purified and derivatized to prepare the water-soluble metallofullerol, Hox@C82(OH)y. This metallofullerol was then neutron-activated (165Ho[n,gamma]166Ho) to prepare the 166Hox@C82(OH)y analog as a radiotracer, which was monitored, after intravenous administration, for up to 48 hours by using dissection radioanalysis, and its biodistribution was compared with a control compound, Na2[166Ho(DTPA)(H2O)]. Results showed selective localization of the 166Hox@C82(OH)y tracer in the liver but with slow clearance, as well as uptake by bone without clearance. In contrast, excretion of the control compound was nearly quantitative after 1 hour. The fate of 166Ho was also explored by a metabolism study of 166Hox@C82(OH)y in Fischer rats. Results indicated 20% excretion of intact 166Hox@C82(OH)y within 5 days. The present findings demonstrate the feasibility of using water-solubilized metallofullerene radiotracers to monitor the fate of fullerene-based materials in animals, and suggest that water-solubilized fullerene materials, in general, may be useful components in drug design.

Radiotoxicity of bismuth-213 bound to membranes of monolayer and spheroid cultures of tumor cells.

Monoclonal antibody 13A to murine CD44 was used to bind the alpha-particle emitter 213Bi to cell surfaces of cultured EMT-6 or Line 1 tumor cells. Data on kinetics and saturation of binding, cell shape and nuclear size were used to calculate the absorbed dose to the nuclei. Treatment of monolayer cells with [213Bi]MAb 13A produced a classical exponential survival curve with no apparent shoulder. Microdosimetry analyses indicated that 1.4-1.7 Gy produced a 37% surviving fraction (D0). Multicellular spheroids were shown to bind [213Bi]MAb 13A mainly on the outer cell layer. Relatively small amounts of activity added to the spheroids resulted in relatively large absorbed doses. The result was that 3-6-fold less added radioisotope was necessary to kill similar fractions of cells in spheroids than in monolayer cells. These data are consistent with the interpretation that the alpha particles from a single 213Bi atom bound to one cell can penetrate and kill adjacent cells. Flow cytometry was used to sort cells originating from the periphery or from the interior of spheroids. Cells from the outside of the [213Bi]MAb 13A exposed spheroids had a lower surviving fraction per administered activity than cells from the interior. Cells were killed efficiently in spheroids up to 20-30 cells in diameter. The data support the hypothesis that alpha-particle emitters should be very efficient at killing cells in micrometastases of solid tumors.

Treatment of lung tumor colonies with 90Y targeted to blood vessels: comparison with the alpha-particle emitter 213Bi.

An in vivo lung tumor model system for radioimmunotherapy of lung metastases was used to test the relative effectiveness of the vascular- targeted beta-particle emitter 90Y, and alpha-particle emitter, 213Bi. Yttrium-90 was shown to be stably bound by CHXa" DTPA-MAb 201B conjugates and delivered efficiently to lung tumor blood vessels. Dosimetry calculations indicated that the lung received 16.2 Gy/MBq from treatment with 90Y MAb 201B, which was a sevenfold greater absorbed dose than any other organ examined. Therapy was optimal for 90Y with 3 MBq injected. Bismuth-213 MAb 201B also delivered a similar absorbed dose (15Gy/MBq) to the lung. Yttrium-90 was found to be slightly more effective against larger tumors than 213Bi, consistent with the larger range of 2 MeV beta particles from 90Y than the 8 MeV alpha particles from 213Bi. Treatment of EMT-6 tumors growing in immunodeficient SCID mice with 90Y or 213Bi MAb 201 resulted in significant destruction of tumor colonies; however, 90Y MAb 201B was toxic for the SCID mice, inflicting acute lung damage. In another tumor model, IC-12 rat tracheal carcinoma growing in SCID mouse lungs, 90Y therapy was more effective than 213Bi at destroying lung tumors. However, 90Y MAb 201B toxicity for the lung limited any therapeutic effect. We conclude that, although vascular-targeted 90Y MAb can be an effective therapeutic agent, particularly for larger tumors, in this model system, acute damage to the lung may limit its application.