“…64 Cu was historically produced by a nuclear reactor, both by carrier‐added neutron activation 63 Cu(n,γ) 64 Cu and under no‐carrier‐added conditions with fast neutrons by 64 Zn(n,p) 64 Cu . The radionuclide is presently produced using a cyclotron via the 64 Ni(p,n) 64 Cu nuclear reaction, with an incident energy of approximately 11 to 14 MeV, although another option being investigated is the 64 Ni(d,2n) 64 Cu production method .…”
Background
64Cu (T1/2 = 12.7 h) is an important radionuclide for diagnostic purposes and used for positron emission tomography (PET). A previous method utilized at Paul Scherrer Institute (PSI) proved to be unreliable and, while a method using anion exchange chromatography is a popular choice worldwide, it was felt a different approach was required to obtain a robust chemical separation method.
Methods
Enriched 64Ni targets were created by electroplating on gold foil. The targets were irradiated with protons degraded to approximately 11 MeV at PSI's Injector 2 72 MeV research cyclotron and subsequently dissolved in HCl. The resultant solution was loaded onto AG MP‐50 cation exchange resin and the 64Cu separated from its target material and radiocobalt impurities, produced as part of the irradiation process, using various specific mixtures of HCl/acetone solution. The eluted product was evaporated and picked up in dilute HCl (0.05 M). The chemical purity of 64Cu was determined by radiolabeling experiments at the highest possible molar activities.
Results
Reproducible results were obtained, yielding 3.6 to 8.3 GBq 64Cu of high radionuclidic and radiochemical purity. The product was labeled to NODAGA‐RGD, achieved at up to 500 MBq/nmol, indicating the high chemical purity. In a proof‐of‐concept in vivo study, 64Cu‐NODAGA‐RGD was used for PET imaging of a tumor‐bearing mouse.
Conclusion
The chemical separation devised to produce high‐quality 64Cu proved to be robust and reproducible. The concept can be used at medical cyclotrons utilizing a solid target station, such that 64Cu can be used at hospitals for PET imaging.
“…64 Cu was historically produced by a nuclear reactor, both by carrier‐added neutron activation 63 Cu(n,γ) 64 Cu and under no‐carrier‐added conditions with fast neutrons by 64 Zn(n,p) 64 Cu . The radionuclide is presently produced using a cyclotron via the 64 Ni(p,n) 64 Cu nuclear reaction, with an incident energy of approximately 11 to 14 MeV, although another option being investigated is the 64 Ni(d,2n) 64 Cu production method .…”
Background
64Cu (T1/2 = 12.7 h) is an important radionuclide for diagnostic purposes and used for positron emission tomography (PET). A previous method utilized at Paul Scherrer Institute (PSI) proved to be unreliable and, while a method using anion exchange chromatography is a popular choice worldwide, it was felt a different approach was required to obtain a robust chemical separation method.
Methods
Enriched 64Ni targets were created by electroplating on gold foil. The targets were irradiated with protons degraded to approximately 11 MeV at PSI's Injector 2 72 MeV research cyclotron and subsequently dissolved in HCl. The resultant solution was loaded onto AG MP‐50 cation exchange resin and the 64Cu separated from its target material and radiocobalt impurities, produced as part of the irradiation process, using various specific mixtures of HCl/acetone solution. The eluted product was evaporated and picked up in dilute HCl (0.05 M). The chemical purity of 64Cu was determined by radiolabeling experiments at the highest possible molar activities.
Results
Reproducible results were obtained, yielding 3.6 to 8.3 GBq 64Cu of high radionuclidic and radiochemical purity. The product was labeled to NODAGA‐RGD, achieved at up to 500 MBq/nmol, indicating the high chemical purity. In a proof‐of‐concept in vivo study, 64Cu‐NODAGA‐RGD was used for PET imaging of a tumor‐bearing mouse.
Conclusion
The chemical separation devised to produce high‐quality 64Cu proved to be robust and reproducible. The concept can be used at medical cyclotrons utilizing a solid target station, such that 64Cu can be used at hospitals for PET imaging.
“…Within the past 10 years, several
laboratories have reported on the measurement of decay data for 64 Cu
(Qaim et al 2007, Wanke et al 2010, Luca
et al 2012, Bé et al
2012). Many of these studies were conducted by National Metrology Institutes
during the course of the development of primary national standards for this
radionuclide.…”
Section: Introductionmentioning
confidence: 99%
“…The first of these was conducted by Singh (2007) as part of the Evaluated Nuclear Data Structure File
(ENSDF), while the most recent was performed by Bé et al (2011) as part of the Decay Data Evaluation Project
(DDEP). Because they were published subsequent to the ENSDF evaluation, the recent
measurements from Wanke et al (2010), Luca et al (2012), and Bé et al (2012) are only considered in the DDEP
evaluation. The evaluated half-life from the DDEP evaluation is (12.7004 ±
0.0020) hours (Bé et al 2011), while
the ENSDF evaluation gives a recommended half-life of (12.701 ± 0.002) hours
(Singh 2007).…”
The National Institute of Standards and Technology (NIST) performed new
standardization measurements for 64Cu. As part of this work the
photon emission probabilities for the main gamma-rays and the half-life were
determined using several high purity germanium (HPGe) detectors. Half-life
determinations were also carried out with a NaI(Tl) well counter and two
pressurized ionization chambers.
“…The precise value of half life is directly used in nuclear medicine units for the calculation of activity at the moment of administration. (Bé et al 2011). RML standardized absolutely solutions from 64 Cu and 68 Ga by the coincidence method .…”
Section: High Resolution Spectrometric Systemmentioning
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