Yttrium-90 and Rhenium-188 Radiopharmaceuticals for Radionuclide Therapy

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with high activities of 90 Sr up to 93 mCi. This 90 Sr/ 90 Y extraction generator was operated for six cycles, giving a mean 90 Y production yield of 65.8% (47.6–86.0 mCi). After purification using cation exchange chromatography, the RCP of 90 Y under acetate form was >99% using TLC and the 90 Sr breakthrough was
12.1.1.4. Acid vapour trap and radioactive waste collection Because of the long half-life of 90 Sr, acid vapour and other radioactive wastes were collected in a closed system after decreasing their volume. Acid vapour from the evaporation flask was evacuated using polyvinyl chloride tubing with an air jet pump (activated by compressed air) and trapped in an acid scrubber unit kept outside the fume hood. The unit had continuous circulating water from a storage tank and the drain returned to the tank. Other radioactive wastes in the process box were then washed and kept in a 20 L storage vessel under the fume hood, with the drainage port located on the box floor. 12.1.2. Strontium-90/yttrium-90 extraction generator Three columns of strontium resin (Eichrom Technologies) were connected in tandem. A concentration of 3M HNO 3 was used as the eluent for 90 Y extraction and 0.05M HNO 3 for 90 Sr recovery. The flow rate of the peristaltic pump was set at 0.5 mL/min and 90 Y was collected for 30 mL in an evaporating flask, which was subsequently heated to dryness. The residue containing the 90 Y product was dissolved with 0.05M HCl. Strontium-90 adsorbed in the first and second columns was recovered with 0.05M HNO 3 (30 mL each) and collected in another evaporation flask, which was then heated to almost dryness for the next cycle. Strontium-90 was used at the tracer level (300–400 µCi) and the low level (6–8 mCi) to monitor the elution characteristics and for evaluation of the generator performance, respectively. 12.1.3. Strontium-90/yttrium-90 ion exchange generator Two ion exchange resin columns (Dowex 50WX8, 100–200 mesh, H + form) were connected in tandem. Strontium-90 was dissolved in 0.003M EDTA, pH4.5, and loaded onto the first column. The generator was eluted with 40 mL of this buffer into an evaporating flask to enable collection of 90 Y in the form of the 90 Y EDTA complex. The eluate was subsequently digested with concentrated H 2 SO 4 /concentrated HNO 3 by heating (300°C) to dryness. This 90 Y was preconditioned for purification by redissolving it in 0.05M HCl. Strontium-90 from the first column was recovered by washing with 20 mL of 2M HNO 3 and 20 mL of 4M HCl and subsequently collected in another evaporating flask. This was then heated to almost dryness for the next cycle. The amount of 90 Sr activity loaded was the same as that used in the 90 Sr/ 90 Y extraction generator. 231
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IAEA RADIOISOTOPES AND RADIOPHARMAC
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YTTRIUM-90 AND RHENIUM-188 RADIOPHA
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IAEA RADIOISOTOPES AND RADIOPHARMAC
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FOREWORD The IAEA helps to promote
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CONTENTS CHAPTER 1. INTRODUCTION ..
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7.4. Discussion ...................
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CHAPTER 12. DEVELOPMENT OF 90 Sr/ 9
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Chapter 1 INTRODUCTION 1.1. BACKGRO
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devices were designed to improve th
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etention of the antibody’s target
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Binding affinity of these derivativ
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Chapter 2 FUNDAMENTAL CONCEPTS IN R
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A special characteristic of radioph
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β particles emitted by 90 Y. Numer
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2.3.1. Exploitation of certain meta
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2.3.3. Antibodies The high specific
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cell cultures, presents one example
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Another very promising form of radi
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destructive processes within the jo
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esearch efforts, since then. Howeve
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[2.18] HAMILTON, J.G., The metaboli
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[2.52] GOLDENBERG, D.M., et al., Mu
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Chapter 3 DEVELOPMENT OF RADIOPHARM
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FIG. 3.3. Elution efficiencies for
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FIG. 3.5. Electrodeposition of yttr
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The results of the experiments of r
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TABLE 3.3. RESULTS FOR 90 Sr/ 90 Y
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FIG. 3.11. Elution yield of a 90 Sr
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According to Fig. 3.12, there is a
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eagent (Sigma). The mean recovery o
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FIG. 3.18. Variation of RCP (%) of
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(20 and 30 min) and volume of 188 R
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FIG. 3.24. Variation of labelling y
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(c) Clodronate: 20 mg of clodronate
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Chapter 4 EVALUATION OF THE 90 Sr/
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Kamadhenu consists of five main com
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Quality control of radiolabelling w
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The electrochemical deposition of 9
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FIG. 4.5. Typical pattern of the wh
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FIG. 4.6. Elution profile from the
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FIG. 4.8. CD20 recognition in Ramos
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4.5. RECOMMENDATIONS AND FUTURE WOR
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adioiodine labelled anti-NCAM antib
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FIG. 5.1. Comparison of biodistribu
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FIG. 5.3. Three step strategy. Biot
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TABLE 5.1. THREE STEP PRETARGETING:
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5.1.4. Therapeutic experiments with
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5.1.4.4. Conclusion The radioiodine
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control procedure for detection of
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6.1.3. Recovery of doped 85/89 Sr 2
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6.2. PREPARATION AND BIOEVALUATION
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(a) (b) (c) FIG. 6.5. PD-10 column
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FIG. 6.7. SDS PAGE pattern of ritux
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FIG. 6.10. HPLC pattern of pure 90
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FIG. 6.13. Cell binding studies wit
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6.2.1.6. Conclusion The procedure f
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FIG. 6.17. Elution profile of 90 Y
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form NADH, which, in turn, causes t
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FIG. 6.19. In vivo distribution pat
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ACKNOWLEDGEMENTS The authors of thi
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Chapter 7 DEVELOPMENT OF THERAPEUTI
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the residual breast tissue becoming
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7.2.5.2. Automatic procedure The la
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FIG. 7.2. RCP values of 90 Y r-BHD
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FIG. 7.3. Pyrogen test shows result
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to avidin at the 1:4 avidin:r-BHD m
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[7.9] SU, F.M., GUSTAVSON, L.M., AX
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8.1. INTRODUCTION In past years, th
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(a) FIG. 8.1. (a) Schematic illustr
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Preliminary synthesis of the biotin
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(a) (b) FIG. 8.4. (a) PEGylated and
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TABLE 8.2. BIODISTRIBUTION IN RATS
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A specific binding to avidin was ev
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[8.13] BOSCHI, A., DUATTI, A., UCCE
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90 Y solution obtained from a 90 Sr
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From each fraction, a ~1 g aliquot
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FIG. 9.2. Relationship between 90 S
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with 188 Re obtained from the 188 W
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9.3.2. Labelling of DPA ale DPA ale
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FIG. 9.8. TLC radiochromatogram of
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(-) 188 Re(CO) 3 (+) (-) 99m Tc(CO)
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the HSA solution containing sodium
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TABLE 9.3. RESULTS OF 99m Tc LABELL
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9.4.4. Yttrium-90 and 177 Lu labell
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FIG. 9.14. In vitro stability of 90
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(a) (b) (c) (d) (e) (f) (g) (h) (i)
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TABLE 9.8. YTTRIUM-90 CITRATE COLLO
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(a) (b) FIG. 9.17. Grain size distr
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TABLE 9.10. BIODISTRIBUTION AFTER A
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FIG. 9.19. Structure of DOTA biotin
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[9.8] WESTERA, G., GADZE, A., HORST
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Chapter 10 DEVELOPMENT, PREPARATION
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acidic pH) and the vial heated for
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10.2.2.1. Materials and methods (a)
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Using a semiquantitative method, th
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FIG. 10.3. Whole body, SPECT and ta
Page 193 and 194: TABLE 10.4. ORGAN DISTRIBUTION STUD
Page 195 and 196: was assessed by measuring the relea
Page 197 and 198: —— Biological studies: The whol
Page 199 and 200: or liver) (see Fig. 10.7). The resu
Page 201 and 202: (b) Results and discussion Healthy
Page 203 and 204: and the pellet (particles of HA lab
Page 205 and 206: FIG. 10.11. Organ distribution stud
Page 207 and 208: The procedure was as follows: —
Page 209 and 210: TABLE 10.5. INFLUENCE OF CHEMICAL I
Page 211 and 212: analysed using ICP OES was within t
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Page 215 and 216: adionuclidic purity of the 90 Y sol
Page 217 and 218: FIG. 10.16. (a) Strontium-90/yttriu
Page 219 and 220: [10.5] DJOKIĆ, D.J., JANKOVIĆ, D.
Page 221 and 222: Yttrium-90 is one of the radionucli
Page 223 and 224: (a) (b) (c) The generator was prepa
Page 225 and 226: —— Development of EPC: The EPC
Page 227 and 228: FIG. 11.4. Elution curve of 90 Sr e
Page 229 and 230: 11.4. YTTRIUM-90 MAbs The use of th
Page 231 and 232: FIG. 11.6. RCP measured using ITLC
Page 233 and 234: FIG. 11.9. Biodistribution of 90 Y
Page 235 and 236: 11.5. YTTRIUM-90 EDTMP Bone metasta
Page 237 and 238: FIG. 11.14. Electrophoresis of 90 Y
Page 239 and 240: FIG. 11.15. Particle size distribut
Page 241 and 242: 11.7. CONCLUSION During this CRP, a
Page 243: Chapter 12 DEVELOPMENT OF 90 Sr/ 90
Page 247 and 248: 12.1.8. Yttrium-90 peptide labellin
Page 249 and 250: (a) FIG. 12.3. Yttrium-90 elution p
Page 251 and 252: FIG. 12.6. HPLC of 90 Y DOTATATE. 1
Page 253 and 254: Chapter 13 BIFUNCTIONAL BISPHOSPHON
Page 255 and 256: latter requirement [13.10]. When th
Page 257 and 258: whether the organometallic core sel
Page 259 and 260: The fate of a targeted imaging prob
Page 261 and 262: FIG. 13.7. SPECT/CT images showing
Page 263 and 264: FIG. 13.9. TLC SG analyses of [ 188
Page 265 and 266: FIG. 13.11. Stability study (toward
Page 267 and 268: Ex vivo biodistribution studies at
Page 269 and 270: was in the form of either pertechne
Page 271 and 272: FIG. 13.19. Absolute uptake of 99m
Page 273 and 274: [13.2] ZHANG, S., GANGAL, G., ULUDA
Page 275 and 276: [13.31] DE ROSALES, R.T.M., et al.,
Page 277 and 278: The activity due to 90 Sr should be
Page 279 and 280: 14.3.1.2. Operation of the 90 Sr/ 9
Page 281 and 282: antibody were taken, to which 90 Y
Page 283 and 284: operation, radiopharmaceutical grad
Page 285 and 286: 14.4.1.3. Operation of the stage II
Page 287 and 288: A typical EPC pattern for a 90 Y pr
Page 289 and 290: FIG. 14.10. Decay curve of carrier
Page 291 and 292: FIG. 14.12. ITLC of 90 Y rituximab.
Page 293 and 294: FIG. 14.13. Reaction scheme for lab
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TABLE 14.6. STABILITY (%) OF 90 Y D
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FIG. 14.18. Microsphere albumin siz
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[14.3] PANDEY, U., DHAMI, P.S., JAG
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naphthalene and 1.2 g of 2,5-diphen
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A-2.2. Materials The method for sep
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out using a Wallac 1411 spectromete
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A-5.3. Procedure The technique was
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Although acyclic chelators offer ma
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(b) (c) and 90 Y colloids, both ser
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CONTRIBUTORS TO DRAFTING AND REVIEW
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INDIA Allied Publishers 1 st Floor,
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A key requirement for the effective
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Yttrium-90 and Rhenium-188 Radiopharmaceuticals for Radionuclide Therapy

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