Excitation functions of 124Te(d,xn)124,125I reactions from threshold up to 14MeV: comparative evaluation of nuclear routes for the production of 124I

Th, Bastian; Hh, Coenen; Sm, Qaim

doi:10.1016/s0969-8043(01)00079-3

Cited by 40 publications

(20 citation statements)

References 17 publications

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“…New cross sections were recalculated from the authors' thin target yield values presented in the same paper. Newly derived data compare very well with those of Bastian et al [4]. In figure 2 experimental data sets are compared with theoretical curves.…”

Section: Deuteron Induced Reaction: 124 Te(d2n) 124 Isupporting

confidence: 68%

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IAEA coordinated research programme: nuclear data for the production of therapeutic radionuclides

Capote

Běták

Carlson

et al. 2007

Nd2007

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Abstract. The need for radioisotopes in cancer therapy is very well established. With a view to providing standardised data for the production of relevant radioisotopes an IAEA Coordinated Research Project on "Nuclear Data for the Production of Therapeutic Radionuclides" was started in 2003, and is now close to completion. Experimental data compilations, theoretical calculations and evaluations were carried out for each of the reactions. The recommendations for both established and emerging radionuclides are discussed. Examples of the analyses carried out to produce the recommended data for some radionuclides are also presented. The improved quality of the nuclear data will make reactor and accelerator production of therapeutic radionuclides much more efficient and effective, and should also enhance their quality through improved purity.

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Section: Deuteron Induced Reaction: 124 Te(d2n) 124 Isupporting

confidence: 68%

“…Two experimental cross section data sets for this reaction are available in the literature [4,5]. The original cross-section values published by Firouzbakht et al [5] were incorrect.…”

Section: Deuteron Induced Reaction: 124 Te(d2n) 124 Imentioning

confidence: 99%

IAEA coordinated research programme: nuclear data for the production of therapeutic radionuclides

Capote

Běták

Carlson

et al. 2007

Nd2007

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“…c: I β + value has rather large uncertainty. 54 Fe(d, n) 55 Co, 86 Sr( p, n) 86 Y and 120 Te( p, n) 120g I reactions, respectively, the level of the 56 Co impurity in 55 Co, of 87 Y in 86 Y and of 120m I in 120g I is much higher. On the other hand, the production of the radionuclides 52 Fe, 73 Se, 77 Kr and 83 Sr demands a high intensity cyclotron, accelerating protons up to about 70 MeV (in the case of 52 Fe preferably up to 100 MeV).…”

Section: Production Using Intermediate Energy Reactionsmentioning

confidence: 91%

“…It was originally produced via the 124 Te(d, 2n) 124 I reaction [53]; accurate cross section data were measured later [54]. Several other reactions have also been investigated [cf .…”

Section: Production Using Low-energy Reactionsmentioning

confidence: 99%

Development of novel positron emitters for medical applications: nuclear and radiochemical aspects

Qaim¹

2011

Ract

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In molecular imaging, the importance of novel longer lived positron emitters, also termed as non-standard or innovative PET radionuclides, has been constantly increasing, especially because they allow studies on slow metabolic processes and in some cases furnish the possibility of quantification of radiation dose in internal radiotherapy. Considerable efforts have been invested worldwide and about 25 positron emitters have been developed. Those efforts relate to interdisciplinary studies dealing with basic nuclear data, high current charged particle irradiation, efficient radiochemical separation and quality control of the desired radionuclide, and recovery of the enriched target material for reuse. In this review all those aspects are briefly discussed, with particular reference to three radionuclides, namely 64 Cu, 124 I and 86 Y, which are presently in great demand. For each radionuclide several nuclear routes were investigated but the ( p, n) reaction on an enriched target isotope was found to be the best for use at a small-sized cyclotron. Some other positron emitting radionuclides, such as 55 Co, 76 Br, 89 Zr, 82m Rb, 94m Tc, 120 I, etc., were also produced via the low-energy ( p, n), ( p, α) or (d, n) reaction. On the other hand, the production of radionuclides 52 Fe, 73 Se, 83 Sr, etc. using intermediate energy ( p, xn) or (d, xn) reactions needs special consideration, the nuclear data and chemical processing methods being of key importance. In a few special cases, a high intensity 3 He-or α-particle beam could be an added advantage. The production of some potentially interesting positron emitters via generator systems, for example 44 Ti/ 44 Sc, 72 Se/ 72 As and 140 Nd/ 140 Pr is considered. The significance of new generation high power accelerators is briefly discussed.

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“…† The preferred production route for 124 I is the 124 Te( p, n) 124 I process [9]. This nuclear reaction leads to good target yields with a 124 I product of the highest radionuclidic purity [10]. Iodine-125 (T 1/2 = 60 d) is the only significant impurity after the decay of 123 I (T 1/2 = 13 h).…”

Section: Introductionmentioning

confidence: 99%

Improved targetry and production of iodine-124 for PET studies

Glaser¹,

Mackay²,

Ranicar³

et al. 2004

Radiochimica Acta

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Iodine-124 (T 1/2 = 4.18 d) is an important radionuclide for preclinical research in positron emission tomography (PET). We describe an improved method to produce and extract 124 I from a solid [ 124 Te]TeO 2 target efficiently using the dry distillation technique. Our process is based on remote hot cell handling and was optimised to achieve efficiencies better than 90% with an average thick target yield of 9.0 ± 1.0 MBq/µAh (n = 47, corrected for decay). The technology is safe and reduces the dose to the operator.

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Excitation functions of 124Te(d,xn)124,125I reactions from threshold up to 14MeV: comparative evaluation of nuclear routes for the production of 124I

Cited by 40 publications

References 17 publications

IAEA coordinated research programme: nuclear data for the production of therapeutic radionuclides

IAEA coordinated research programme: nuclear data for the production of therapeutic radionuclides

Development of novel positron emitters for medical applications: nuclear and radiochemical aspects

Improved targetry and production of iodine-124 for PET studies

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