212Pb@C60 and Its Water-Soluble Derivatives
A R T I C L E S
440.4 keV (26.1%), respectively. To quantitate 212Bi, the intensity of
the 583.1 keV (32.5%) γ-ray of its 3.07-min 208Tl daughter was
measured at transient equilibrium with the parent. Consequently, at least
10 min were allowed to elapse between chemical processing and activity
measurements. Since the intensity of the γ-ray from 225Ac at 188.1
keV is only 0.47%, 225Ac was quantitated by measurement of intensities
of 218.0 keV (11.58%) from its 4.9-min 221Fr daughter at transient
equilibrium. All relevant nuclear data are taken from the 1986 Table
of Radioisotopes.17 Gross radioactivity was measured in an ionization
chamber (CRC-7, Capintec Inc., NJ). An automated γ-ray scintillation
counter (Wallac Wizard) consisting of a well-type NaI(Tl) detector was
used for biodistribution studies of 212Pb.
Synthesis by Recoil. The 224/225Ra sources were prepared by an
electrodeposition technique. The electrolysis apparatus was of conven-
tional design consisting of a 20-mL Pyrex vial, a Pt working electrode
(1.5 mm o.d. Pt rod bent into a circle and spot welded to a ∼1 cm
diameter circle of Pt mesh), and a counter Pt electrode (1.5 mm o.d.
rod). The distance between the two electrodes was ∼5 mm. The
electrolyte, 10 mL of 0.01 M HNO3, was purged with a gentle flow of
N2. In a typical experiment, the purified 224Ra (as dry nitrate) was
dissolved in 200 µL of 1.2 M HNO3, and the mixture was transferred
to the electrolysis cell. Electrodeposition was conducted under a constant
potential of 12 V. Under our experimental setup, the initial current
was ∼0.5 mA, which dropped to ∼0.1 mA over a 2-h period. When
assay of the electrolyte indicated removal of 224Ra from solution, the
working electrode was carefully removed from the electrolysis cell
without opening the circuit. The working electrode was then left to
dry in air for 2 h and assayed for radioactivity.
parent, 212Pb (τ1/2 ) 10.6 h), as a vehicle for transporting 212Bi
to the target tissue. However, while the PAC chelator known
as DOTA (1,4,7,10-tetraazacyclododecane-N,N′,N′′,N′′′-tetraace-
tic acid) can chelate 212Pb satisfactorily in saline solutions, in
vivo tests resulted in severe myelotoxicity,14 presumably the
result of bone-targeting 212Pb2+ lost or transchelated out of the
DOTA. Furthermore, 36% internal conversion of the γ-ray
which follows the â-decay of 212Pb to 212Bi also caused release
of 36% of 212Bi from DOTA.15 Since we began this work, two
reports of new chelators for 212Pb have appeared,16 but the results
appear to indicate that further development or a new approach
is still required. It was thought that use of a fullerene instead
of a chelator could potentially solve both problems with 212Pb,
thereby making the 212Pb/212Bi system attractive for RIT. If the
fullerene was successful, the only significant remaining draw-
back to using 212Pb in RIT is the high-energy γ-ray emitted by
the 208Tl daughter. Compared to the outstanding problems with
225Ac and 213Bi, solutions for shielding health-care personnel
from high-energy γ-rays are well known and relatively inex-
pensive compared to the costs of 211At production. Thus,
development of endohedral 212Pb fullerenes could make R-par-
ticle RIT feasible, greatly impacting the way hematological
malignancies and micrometastes are treated.
In this paper, we report the synthesis of 212Pb@C60 by recoil
following R-decay of its short-lived parent, formation of water-
soluble 212Pb@C60 malonic acids, the stability of the radio-
fullerene during â--decay of 212Pb to 212Bi, and a preliminary
biodistribution study of the untargeted water-soluble radio-
fullerene in mice. To our knowledge, this is the first report of
an endohedral fullerene formed by recoil from R-decay, the first
endohedral lead fullerene, the first fullerene encapsulating an
R-emitting radionuclide with a therapeutically useful half-life,
and (despite some limitations) the first biodistribution study of
radiofullerene malonic acids.
A coating of C60 was applied by spraying a saturated toluene solution
of C60 over the mesh with an artist’s airbrush. The toluene rapidly
evaporated, leaving a thick film of C60 over the radionuclide-plated Pt
mesh. The coated mesh was then left to stand for 24-36 h, except as
noted. At the end of this contact time, the coated Pt mesh was assayed
for radioactivity.
Esterification. Because M@C60 are generally insoluble,18 the
fullerenes (both C60 and R@C60) were removed from the Pt mesh by
derivatizing them to their malonic ester derivatives,19 which are then
soluble in tetrahydrofuran (THF) and ethyl acetate (EA). After assaying
for radioactivity, the mesh was placed in a two-neck 10-mL pear-shaped
flask which was purged with argon. Four milliliters of THF containing
3 mg of suspended and dispersed NaH was added. Diethylbromoma-
lonate (0.02 mL) was also added, and the flask was vortexed vigorously
for 10 min. The THF slurry was transferred by syringe from the flask
into a 15-mL polypropylene conical bottom centrifuge tube and
centrifuged for 2 min at ∼1000g to sediment the sodium salts. The
supernatant was transferred by syringe into a fresh centrifuge tube and
evaporated under argon. A 0.75 mL amount of EA was added, vortexed
briefly to dissolve the fullerene esters, and then transferred to a 1.5
mL conical-bottomed centrifuge tube. Alternately, the THF could be
evaporated in the flask, 0.75 mL of EA added, vortexed, removed to a
1.5 mL centrifuge tube, and centrifuged for 1 min at 10 000g to
sediment the NaH. The EA supernatant was then transferred to a fresh
1.5 mL conical-bottomed centrifuge tube. The mesh was assayed again
for radioactivity at a later convenient time.
Experimental Section
Radioisotopes. As needed, 224Ra and 225Ra were extracted from a
stock of Th containing both 228Th and 229Th. Chemical separation of
Ra and Ac from Th was achieved using the macroporous anion-
exchange resin MP1 in 8 M HNO3 media, and separation of Ra from
Ac was accomplished on a low-cross-linking cation-exchange resin
AG50-X4 using 1.2 M HNO3 as eluent. A detailed procedure for these
separations is given by Boll et al.7a At the time of separation, the activity
ratio of 224Ra to 225Ra was 1:2.5.
Radioactivity Measurement. γ-ray spectrometry was used for
measurement of all radioisotopes used in this study. The γ-ray
spectrometer consisted of a calibrated intrinsic Ge detector (crystal
active volume ≈ 100 cm3) and a PC-based multichannel analyzer
(MCA) (Canberra Industries, Meriden, CT). The detector has a
resolution of 0.8 keV at 5.9 keV, 1.0 keV at 123 keV, and 1.9 keV at
1332 keV. Energy and efficiency calibrations were determined with
γ-ray sources traceable to the National Institute of Standard and
Technology (NIST). The γ-ray energies and their absolute intensities
in parentheses used for determination of 212Pb, 224Ra, 225Ra, and 213Bi
radioactivity were 238.6 (43.6%), 240.8 (3.90%), 40.1 (30.0%), and
Removal of Unencapsulated Radionuclides. Free or otherwise
unencapsulated radionuclides were removed by repeated washings of
the EA ester solution with an aqueous 0.012 M HNO3 solution that
was also 5 µN in each of cold Pb2+, Bi3+, and Tl3+ ions. One-half
milliliter of the washing solution was added to the EA and vortexed
for 10 s, followed by centrifugation at 2000 rpm for 30 s. The upper
organic layer was carefully removed by a syringe with a fine-gauge
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Oncol. Biol. Phys. 1996, 34, 609-616. (b) Horak, E.; Hartmann, F.;
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S.; Milenic, D. E.; Garmestani, K.; Brady, E. D.; Arora, H.; Pfiester, C.;
Brechbiel, M. W. Nucl. Med. Biol. 2006, 33, 459-467.
(17) Browne, E.; Firestone, R. B. In Table of Radioisotopes; Shirley, V. S.,
Ed.: Wiley-Interscience: New York, 1986.
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(19) Bolskar, R. D.; Benedetto, A. F.; Husebo, L. O.; Price, R. E.; Jackson, E.
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