New measurements of excitation functions of 186W(p,x) nuclear reactions up to 65MeV. Production of a 178W/178mTa generator

Tárkányi, F.; Ditrói, F.; Takács, S.; Hermanne, Alex

doi:10.1016/j.nimb.2016.11.027

Cited by 11 publications

(6 citation statements)

References 24 publications

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“…5,77 The 124 Te(p,n) 124 I reaction on 99.8% enriched target over the energy range E p = 12 → 8 MeV has now become the method of choice. The yield of 124 I is not very high, but the product obtained is of the highest radionuclidic purity, the level of the associated long-lived Figure 1, we therefore show the theoretically calculated excitation function of the 124 Te(p,γ) 125 I reaction, as reported in the data file TENDL-2015, 78 which is based on the calculation code TALYS. This code reproduces the measured (p,γ) data within about 30%.…”

Section: I (T ½ = 418 D)mentioning

confidence: 98%

“…The production of 186 Re in no‐carrier‐added form has hitherto been investigated using 2 methods, namely, 186 W(p,n) 186 Re and 186 W(d,2n) 186 Re. Most of the studies deal with nuclear reaction cross section measurements . A critical analysis of data showed that, for obtaining a high‐purity product, an enriched 186 W target is absolutely necessary.…”

Section: Novel Radionuclides For Internal Radiotherapymentioning

confidence: 99%

“…For production of 124 I, initially, the reaction 124 Te(d,2n) 124 I was used. 66 Later on, cross sections of the reactions 124 Te(p,n) 124 I, 125 Te(p,2n) 124 I, and 126 Te(p,3n) 124 I as well as of 3 He-and α particle-induced reactions on antimony (natural and isotopically enriched isotopes) were measured over energy ranges of up to 100 MeV. [67][68][69][70][71][72][73][74] A critical analysis of all the reactions was performed, 75,76 and it was concluded that the 124 Te(p,n) 124 I reaction 67 is the most suitable for the production of 124 I.…”

Section: I (T ½ = 418 D)mentioning

confidence: 99%

“…The enriched target material is regenerated (without any substantial loss) for reuse. 123 I reactions (measured), 67 and of the 124 Te(p,γ) 125 I reaction (calculated). 78 The suitable energy range for the production of 124 I is E p = 12 → 8 MeV The use of a Te-metal target followed by a wet chemical separation of radioiodine has not been very successful.…”

Section: I (T ½ = 418 D)mentioning

confidence: 99%

“…Most of the studies deal with nuclear reaction cross section measurements. [119][120][121][122][123][124][125] A critical analysis of data showed 126 that, for obtaining a high-purity product, an enriched 186 W target is absolutely necessary. The calculated yield of 186 Re from the evaluated excitation function of the 186 W(p,n) 186 Re reaction over E p = 18 → 8 MeV amounts to 4.4 MBq/μA·h and from the 186 W(d,2n) 186 Re reaction over E d = 18 → 8 MeV to 15.8 MBq/μA·h.…”

Section: Re (T ½ = 378 D)mentioning

confidence: 99%

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Development of novel radionuclides for medical applications

Qaim

Spahn

2017

Labelled Comp Radiopharmac

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Medical radionuclide production technology is well established. There is, however, a constant need for further development of radionuclides. The present efforts are mainly devoted to nonstandard positron emitters (eg, Cu, Y, I, and Se) and novel therapeutic radionuclides emitting low-range β particles (eg, Cu and Re), conversion or Auger electrons (eg, Sn and Br), and α particles (eg, Ac). A brief account of various aspects of development work (ie, nuclear data, targetry, chemical processing, and quality control) is given. For each radionuclide under consideration, the status of technology for clinical scale production is discussed. The increasing need of intermediate-energy multiple-particle accelerating cyclotrons is pointed out.

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Section: I (T ½ = 418 D)mentioning

confidence: 98%

Section: Novel Radionuclides For Internal Radiotherapymentioning

confidence: 99%

Section: I (T ½ = 418 D)mentioning

confidence: 99%

Section: I (T ½ = 418 D)mentioning

confidence: 99%

Section: Re (T ½ = 378 D)mentioning

confidence: 99%

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Development of novel radionuclides for medical applications

Qaim

Spahn

2017

Labelled Comp Radiopharmac

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Upgrade of recommended nuclear cross section data base for production of therapeutic radionuclides

Tárkányi

Hermanne

Ignatyuk

et al. 2022

J Radioanal Nucl Chem

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The IAEA Nuclear Data Section has coordinated several actions to setup and improve a database for recommended cross sections and nuclear decay data for various charged-particle reactions that can be used for medical radionuclide production. Some of the earlier evaluations did not provide uncertainties for the recommended cross sections. Updated evaluations with uncertainty quantification for 25 reactions relevant for production of 67Cu, 103Pd, 102mgRh, 114mIn, 125I, 169Yb, 177gLu, 186Re, 192Ir and 210,211At therapeutic radioisotopes are presented. Recommended cross-section data and their uncertainties for production of therapeutic radionuclides are available on the Web page of the IAEA Nuclear Data Section at https://nds.iaea.org/radionuclides and also at the IAEA medical portal https://nds.iaea.org/medportal.

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