Defining Processing Times for Accelerator Produced 225Ac and Other Isotopes from Proton Irradiated Thorium

Fitzsimmons, Jonathan; Griswold, Justin; Medvedev, Dmitri; Cutler, Cathy S.; Mausner, L.F.

doi:10.3390/molecules24061095

Cited by 10 publications

(9 citation statements)

References 14 publications

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“…The radiopurity of 225 Ac will likely be the first specification that fails. The Trilab team has estimated the radiopurity post purification in the presence of 227 Ac and 227 Ac and daughters for BLIP produced 225 Ac from Th targets 18 . Removal of 223 Ra and 227 Th would increase the radiopurity of 225 Ac produced from a Th target at BLIP.…”

Section: Discussionmentioning

confidence: 99%

“…The studies reported herein seek to synthesize, characterize, and evaluate PCST inorganic ion exchanger in the separation process of 225 Ac from irradiated Th target. During the accelerator production of 225 Ac from a 232 Th target 227 Ac and the daughters of 227 Ac are coproduced 18 . The daughters of 227 Ac ( 227 Th and 223 Ra) can be separated from 225 Ac during the purification process 19 .…”

Section: Introductionmentioning

confidence: 99%

“…The daughters of 227 Ac ( 227 Th and 223 Ra) can be separated from 225 Ac during the purification process 19 . However after purification the 227 Ac would grow in and reduce the purity of 225 Ac 18 . Various literature studies to purify 225 Ac from Thorium and/or radium have focused on organic cation or anion ion exchange resins 1,2 .…”

Section: Introductionmentioning

confidence: 99%

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The application of poorly crystalline silicotitanate in production of 225Ac

Fitzsimmons

Abraham

Catalano

et al. 2019

Sci Rep

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Actinium-225 ( 225 Ac) can be produced from a Thorium-229/Radium-225 ( 229 Th/ 225 Ra) generator, from high/low energy proton irradiated natural Thorium or Radium-226 target. Titanium based ion exchanger were evaluated for purification of 225 Ac. Poorly crystalline silicotitanate (PCST) ion exchanger had high selectivity for Ba, Ag and Th. 225 Ac was received with trace amounts of 227 Ac, 227 Th and 223 Ra, and the solution was used to evaluate the retention of the isotopes on PCST ion exchanger. Over 90% of the 225 Ac was recovered from PCST, and the radiopurity was >99% (calculated based on 225 Ac, 227 Th, and 223 Ra). The capacity of the PCST inorganic ion exchange for Barium and 232 Th was determined to be 24.19 mg/mL for Barium and 5.05 mg/mL for Thorium. PCST ion exchanger could separate 225 Ac from isotopes of Ra and Th, and the process represents an interesting one step separation that could be used in an 225 Ac generator from 225 Ra and/or 229 Th. Capacity studies indicated PCST could be used to separate 225 Ac produced on small 226 Ra targets (0.3–1 g), but PCST did not have a high enough capacity for production scale Th targets (50–100 g).

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Section: Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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The application of poorly crystalline silicotitanate in production of 225Ac

Fitzsimmons

Abraham

Catalano

et al. 2019

Sci Rep

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“…Researches are currently underway to find out alternative methods to produce 225 Ac. For example, the Tri-lab project team is looking into ways to directly extract 225 Ac from a proton-irradiated thorium target, and produced 81.4 GBq of 225 Ac in a 10-day irradiation of 200 MeV proton beam at 165 μA 10 , 11 . Regarding this method, one concern is ~ 0.3% yield of 227 Ac contaminating 225 Ac in addition to the relatively high proton energy required.…”

Section: Introductionmentioning

confidence: 99%

Feasibility of a novel photoproduction of 225Ac and 227Th with natural thorium target

Kim

2022

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We propose an innovative way to produce both 225Ac and 227Th, two precious radioisotopes enabling promising targeted alpha therapy, in a natural thorium target bombarded with a 30–90 MeV electron beam. Bremsstrahlung photons in the target are analyzed by MCNP and in-situ photonuclear transmutation of 232Th is evaluated by using the TENDL nuclear data. In the photo-transmutation analysis, 13 nuclides including 229Th and 231Pa are modelled. Special procedures with chemical separations are also proposed to produce pure 225Ac and 227Th in separate streams. In addition, performance of the new approach is compared with conventional methods in terms of the 225Ac and 227Th yields. After a Th target is bombarded with a 500 kW electron beam for a year, yearly 225Ac yield is ~ 8.47 GBq (semi-permanently) and yearly 227Th yield is ~ 48.9 GBq over 50 years, and their yields are at least doubled in a 2-year irradiation. This work will help increase global supply of the two precious isotopes and would invariably help advance TAT-related researches and developments.

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“…The ratio of fission products/ 225 Ac is 12:1, and the radionuclides that are produced are from all the different groups in the periodic table [11]. During the proton irradiation of a thorium target, 227 Ac and 226 Ac are coproduced, and recently published literature discusses their impact on production [12].…”

Section: Introductionmentioning

confidence: 99%

Optimization of Cation Exchange for the Separation of Actinium-225 from Radioactive Thorium, Radium-223 and Other Metals

et al. 2019

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Actinium-225 (225Ac) can be produced with a linear accelerator by proton irradiation of a thorium (Th) target, but the Th also underdoes fission and produces 400 other radioisotopes. No research exists on optimization of the cation step for the purification. The research herein examines the optimization of the cation exchange step for the purification of 225Ac. The following variables were tested: pH of load solution (1.5–4.6); rinse steps with various concentrations of HCl, HNO3, H2SO4, and combinations of HCl and HNO3; various thorium chelators to block retention; MP50 and AG50 resins; and retention of 20–45 elements with different rinse sequences. The research indicated that HCl removes more isotopes earlier than HNO3, but that some elements, such as barium and radium, could be eluted with ≥2.5 M HNO3. The optimal pH of the load solution was 1.5–2.0, and the optimized rinse sequence was five bed volumes (BV) of 1 M citric acid pH 2.0, 3 BV of water, 3 BV of 2 M HNO3, 6 BV of 2.5 M HNO3 and 20 BV of 6 M HNO3. The sequence recovered >90% of 225Ac with minimal 223Ra and thorium present.

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Defining Processing Times for Accelerator Produced 225Ac and Other Isotopes from Proton Irradiated Thorium

Cited by 10 publications

References 14 publications

The application of poorly crystalline silicotitanate in production of 225Ac

The application of poorly crystalline silicotitanate in production of 225Ac

Feasibility of a novel photoproduction of 225Ac and 227Th with natural thorium target

Optimization of Cation Exchange for the Separation of Actinium-225 from Radioactive Thorium, Radium-223 and Other Metals

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