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ABSTRACT: Bei der Behandlung des Prostatakarzinoms ist die Festlegung des korrekten Ausgangsstadiums zur Wahl der am besten geeigneten
primären Therapieform ebenso wie die möglichst frühzeitige Lokalisation eines lokalen Rezidivs oder einer Metastase bei Wiederanstieg
des PSA-Wertes von außerordentlich großer Bedeutung. Mit den derzeit zur Verfügung stehenden morphologisch- und metabolisch-bildgebenden
Verfahren sind diese Fragen jedoch nicht mit ausreichend hoher Genauigkeit zu beantworten, da gerade kleine Metastasen von
unter 1 cm Größe der bisher eingesetzten Bildgebung oftmals entgehen. In den letzten Jahren sind in der Positronenemissionstomographie
(PET) neue radioaktiv markierte Substanzen eingeführt worden, die möglicherweise die bisherigen Schwächen im Rahmen der Diagnostik
des Prostatakarzinoms ausgleichen können. Neben dem 11C- oder 18F-markierten Cholin scheint das [11C]Acetat ein vielversprechender PET-Tracer zu sein. In der vorliegenden Arbeit werden die einzelnen PET-Tracer diskutiert
und anhand von 3 Falluntersuchungen Stärken und Schwächen des [11C]Acetat in der Zusammenschau mit anderen bildgebenden Verfahren und der Histologie gewertet.
Der diagnostische Einsatz des [11C]Acetat beim Prostatakarzinom ist möglich und erscheint hilfreich. Zum jetzigen Zeitpunkt kann die Bedeutung des [11C]Acetat gegenüber anderen diagnostischen Methoden bei den Fragen einer initialen Lymphknotenbeteiligung oder frühzeitigen
Rezidiv-/Metas-tasenlokalisation nach Wiederanstieg des PSA-Wertes sowie bei der Differenzierung Prostatakarzinom – Prostatitis
– benigne Prostatahyperplasie noch nicht abschließend beurteilt werden.
The exact staging of prostate cancer is mandatory to allow selection of the appropriate primary therapy. In addition, if the
PSA level rises again it is extremely important to find the site(s) of local recurrence or metastatic spread as soon as possible.
However, with the morphological and metabolic imaging techniques currently available it is often not possible to answer these
questions with adequate sensitivity and specificity, since small metastases ≤1 cm in diameter are likely to remain undetected
by them. In the last few years new radioactive labelled tracers have been introduced for use in positron emission tomography
(PET), and it is hoped that the shortcomings in the diagnostic procedures used for prostate carcinoma might be compensated
by their use. Besides 11C- or 18F-labelled choline, [11C]Acetate is also attracting attention as a promising PET tracer. In this paper we review the various PET tracers available
and evaluate the advantages and the drawbacks of [11C]Acetate in three case studies by comparing [11C]Acetate-PET with histology and with other imaging techniques.
The use of [11C]Acetate appears to be feasible and helpful in the diagnosis of prostate carcinoma. However, its final value relative to
other imaging techniques needs further investigation, with special reference to initial lymph node involvement, early localisation
of recurrence and possible noninvasive differentiation between prostate cancer, prostatitis and benign hyperplasia of the
prostate.
Der Urologe 04/2012; 41(6):569-576. · 0.50 Impact Factor
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ABSTRACT: Excitation functions of the reactions 55 Mn(p,n) 55 Fe, 55 Mn(p,x) 54 Mn and 55 Mn(p,x) 51 Cr were measured from their respective thresholds up to 18 MeV in the first case and up to 45 MeV in the latter two cases, using the conventional stacked-foil technique. The radioactivity of 55 Fe was determined via high resolution X-ray spectrometry, both non-destructively and after radiochem-ical separation, and of the other radionuclides via high resolution γ-ray spectrometry. Nuclear model calculations were performed using the codes ALICE-IPPE, EMPIRE and TALYS. In some cases good agreement was found between the experimental and theoretical data while in others considerable deviations were observed. From the experimental data the integral yields of the three investigated radionuclides were calculated.
Journal- Korean Physical Society 09/2011; 5960(25). · 0.45 Impact Factor
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ABSTRACT: The lighter, positron emitting isotopes 75 Br and 76 Br have already been in use for some time in molecular imaging with PET. The two Auger electron emitters 77 Br and 80m Br are of potential interest for internal radiotherapy. In this work new cross section measurements were done on nine (p,xn) reactions on enriched Se targets up to 80 MeV. Thin samples were irradiated in a stacked-foil arrangement. The produced radioactivity was measured non-destructively using HPGe detector γ-ray spectrometry. Concerning 80m Br, a special low-energy HPGe detector was used. From the cross section data on the formation of 75 Br, 76 Br, 77 Br and 80m Br their possible production yields have been deduced and the issue of radionuclidic purity is discussed. Whereas an efficient production of 75 Br is only achievable via intermediate energy reactions above 30 MeV, 76 Br and 77 Br can be produced both with proton energies below 25 MeV as well as with intermediate energy protons up to 70 MeV. The production of 80m Br appears to be a good application of small accelerators.
Journal- Korean Physical Society 08/2011; 59(25). · 0.45 Impact Factor
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ABSTRACT: Excitation functions of (α,xn) reactions on 98.28% enriched (123)Sb and on (nat)Sb were measured from 9 to 40 MeV. The data could be described well in terms of statistical and precompound models using the code TALYS. The discrepancies in the literature data for the formation of (125)I and (126)I were solved. The nuclear reaction (123)Sb(α,3n)(124)I on an enriched target appears to be interesting for the production of (124)I (T(1/2)=4.18 d) over the energy range E(α)=42→32 MeV, its yield being 11.7 MBq/μAh. The levels of the radionuclidic impurities (125)I and (126)I amount to 1.8% and 0.6%, respectively. The use of (nat)Sb as target material for (124)I production is unsuitable due to the high level of (123)I impurity.
Applied radiation and isotopes: including data, instrumentation and methods for use in agriculture, industry and medicine 04/2011; 69(4):699-704. · 1.09 Impact Factor
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ABSTRACT: Some production aspects of the Auger electron emitter 193m Pt (T 1/2 = 4.33 d) through the 192 Os(α, 3n)-process were investigated. Relatively thick targets of 99.65% enriched 192 Os, prepared by pressing or electrolytic deposition, were irradiated with 40 MeV α-particles for 3 h at a nominal beam current of 1.6 µA. The radioplatinum formed was chemically separated with a yield of 90% and the expensive target mate-rial was recovered with a yield of 85%. The radioactivity of 193m Pt was determined by high resolution X-ray spectrometry. The radionuclidic purity of 193m Pt amounted to 99%, the level of 195m Pt and 191 Pt impurities being each 0.5%. The batch yield of 193m Pt achieved was about 10 MBq with a specific activity of 1 GBq/µg Pt. Both the batch yield and the specific activity could be appreciably increased through improved tar-getry. A comparison of the cyclotron and reactor production routes of 193m Pt shows that the (n, γ) reaction leads to high production yields but the α-particle induced reaction results in a product of higher radionuclidic purity and four orders of magnitude higher specific activity of 193m Pt.
Radiochimica Acta 03/2011; 99(99):131-1351807. · 1.58 Impact Factor
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H Herzog,
K-J Langen,
C Weirich,
E Rota Kops,
J Kaffanke,
L Tellmann,
J Scheins,
I Neuner,
G Stoffels,
K Fischer,
L Caldeira, H H Coenen,
N J Shah
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ABSTRACT: After the successful clinical introduction of PET/CT, a novel hybrid imaging technology combining PET with the versatile attributes of MRI is emerging. At the Forschungszentrum Jülich, one of four prototypes available worldwide combining a commercial 3T MRI with a newly developed BrainPET insert has been installed, allowing simultaneous data acquisition with PET and MRI. The BrainPET is equipped with LSO crystals of 2.5 mm width and Avalanche photodiodes (APD) as readout electronics. Here we report on some performance characteristics obtained by phantom studies and also on the initial BrainPET studies on various patients as compared with a conventional HR+ PET-only scanner. MATERIAL, METHODS: The radiotracers [18F]-fluoro-ethyl-tyrosine (FET), [11C]-flumazenil and [18F]-FP-CIT were applied. RESULTS: Comparing the PET data obtained with the BrainPET to those of the HR+ scanner demonstrated the high image quality and the superior resolution capability of the BrainPET. Furthermore, it is shown that various MR images of excellent quality could be acquired simultaneously with BrainPET scans without any relevant artefacts. DISCUSSION, CONCLUSION: Initial experiences with the hybrid MRI/BrainPET indicate a promising basis for further developments of this unique technique allowing simultaneous PET imaging combined with both anatomical and functional MRI.
Nuklearmedizin 02/2011; 50(2):74-82. · 1.28 Impact Factor
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K-J Langen,
P Bartenstein,
H Boecker,
P Brust, H H Coenen,
A Drzezga,
F Grünwald,
B J Krause,
T Kuwert,
O Sabri,
K Tatsch,
W A Weber,
M Schreckenberger
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ABSTRACT: For the primary diagnosis of brain tumours, morphological imaging by means of magnetic resonance imaging (MRI) is the current method of choice. The complementary use of functional imaging by positron emitting tomography (PET) and single photon emitting computerized tomography (SPECT) with labelled amino acids can provide significant information on some clinically relevant questions, which are beyond the capacity of MRI. These diagnostic issues affect in particular the improvement of biopsy targeting and tumour delineation for surgery and radiotherapy planning. In addition, amino acid labelled PET and SPECT tracers are helpful for the differentiation between tumour recurrence and non-specific post-therapeutic tissue changes, in predicting prognosis of low grade gliomas, and for metabolic monitoring of treatment response. The application of dynamic PET examination protocols for the assessment of amino acid kinetics has been shown to enable an improved non-invasive tumour grading. The purpose of this guideline is to provide practical assistance for indication, examination procedure and image analysis of brain PET/SPECT with labelled amino acids in order to allow for a high quality standard of the method. After a short introduction on pathobiochemistry and radiopharmacy of amino acid labelled tracers, concrete and detailed information is given on the several indications, patient preparation and examination protocols as well as on data reconstruction, visual and quantitative image analysis and interpretation. In addition, possible pitfalls are described, and the relevant original publications are listed for further information.
Nuklearmedizin 01/2011; 50(4):167-73. · 1.28 Impact Factor
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ABSTRACT: For determination of cross sections of alpha-particle induced reactions on 99.65% enriched (192)Os, the methods for electrolytic preparation of thin samples and radiochemical separation of radioplatinum were optimized. The excitation functions of the (192)Os(alpha,n)(195m)Pt and (192)Os(alpha,3n) (193m)Pt reactions were measured from 20 to 39 MeV. The cross section of the latter reaction reaches a maximum value of about 1.5b at an energy around 36 MeV. The results of nuclear model calculations using the codes TALYS and STAPRE agreed well with the measured data. The optimum energy range for the production of no-carrier-added (193m)Pt (T(1/2)=4.33 d) was found to be E(alpha)=40-->30 MeV. The thick target yield amounts to 10 MBq/microA h and a possible batch yield of 2 GBq should be sufficient for Auger electron therapy on a wide scale.
Applied radiation and isotopes: including data, instrumentation and methods for use in agriculture, industry and medicine 10/2010; 68(10):2001-6. · 1.09 Impact Factor
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ABSTRACT: 77 Br / 80m Br / Intermediate energy / Proton induced reaction / Excitation function / Integral yield / Radionuclide production Summary. The two Auger electron emitting radionuclides of bromine, namely 77 Br (T 1/2 = 57.04 h) and 80m Br (T 1/2 = 4.4 h), are promising candidates for internal radiotherapy. In this work, nuclear reaction cross sections were determined for their production using enriched Se targets. Thin Se sam-ples were irradiated with incident protons of energies up to 85 MeV and the induced radioactivity was measured via non-destructive γ -ray spectroscopy, allowing the determination and extension of the excitation functions of the four reactions 77,78,80 Se(p, xn) 77 Br and 80 Se(p, n) 80m Br. The possible thick target yields were calculated and the different production routes discussed, especially with regard to the yield and the radionuclidic purity of the produced radionuclides.
Radiochimica Acta 06/2010; · 1.58 Impact Factor
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ABSTRACT: In search of an alternative production route of the therapeutically and environmentally interesting radionuclide (191)Pt (T(1/2)=2.8 d), excitation function of the (192)Os((3)He,4n)(191)Pt reaction was measured from its threshold up to 36 MeV. Thin samples of enriched (192)Os were prepared by electrodeposition on Ni-foils, and the conventional stacked-foil technique was used for cross-section measurements. The experimental data were compared with the results of theoretical calculations using the codes ALICE-IPPE and TALYS. Good agreement was found with TALYS. The theoretical thick target yield of (191)Pt over the energy range E(3He)=36-->25 MeV amounts to 6.7 MBq/microA h. A comparison of various investigated production methods of (191)Pt is given. The here investigated (192)Os((3)He,4n)-process leads to very high-purity (191)Pt (>99.5%).
Applied radiation and isotopes: including data, instrumentation and methods for use in agriculture, industry and medicine 12/2008; 67(6):1074-7. · 1.09 Impact Factor
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ABSTRACT: Positron emission tomography (PET) imaging of non-standard positron emitters is influenced by gamma-coincidences, i.e. false coincidences produced by the coincident detection of an annihilation photon and a gamma-ray simultaneously emitted with the positron. The extent to which the PET study is disturbed by this effect is dependent on the kind of the positron emitter used, the kind and position of the object, the acquisition mode, i.e. the optional use of septa, and the reconstruction program. In order to demonstrate and study imaging problems with non-standard positron emitters, a phantom was scanned containing non-radioactive rods with different absorption materials and filled with either (124)I or (86)Y in the bidimensional (2D) as well as tridimensional (3D) acquisition mode.
For reconstruction, the PET manufacturer's standard software without any modification was used. To reduce errors caused by the gamma-coincidences, a simple linear background subtraction, estimated from the counts at the scanner's external radius, was applied.
Without background subtraction, apparent positive and negative ''radioactivity concentrations'' were found in regions of interest positioned over the non-radioactive rods with values higher for (86)Y compared to (124)I and also higher for 3D compared to 2D. A complete subtraction of the background led to erroneous
The errors in the phantom's non-radioactive rods and the difference between measured and true radioactivity became minimum, when about 75% of the background was subtracted. This refers to both the 2D and 3D mode.
Quantitation problems with the non-standard positron emitters (124)I and (86)Y could be minimized in the phantom study examined here by using a simple background subtraction together with the manufacturer's standard correction and reconstruction procedures.
The quarterly journal of nuclear medicine and molecular imaging: official publication of the Italian Association of Nuclear Medicine (AIMN) [and] the International Association of Radiopharmacology (IAR), [and] Section of the Society of... 07/2008; 52(2):159-65.
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ABSTRACT: For the production of therapy-relevant radionuclides (193m)Pt (T(1/2)=4.33 d) and (195m)Pt (T(1/2)=4.03 d) with a high specific activity, the (192)Os(alpha,n)(195m)Pt and (192)Os(alpha,3n)(193m)Pt nuclear reactions were investigated for the first time from their respective thresholds up to 28 MeV. Thin samples of enriched (192)Os were prepared by electrodeposition on Ni, and the conventional stacked-foil technique was used for cross-section measurements. The calculated thick target yields were found to be 0.013 MBq/microA h for the (192)Os(alpha,n)(195m)Pt reaction in the energy range of E(alpha)=24-->18 MeV, and 0.25 MBq/microA h for the (192)Os(alpha,3n)(193m)Pt reaction in the energy range of E(alpha)=28-->24 MeV. The two radionuclides could not be detected in the interactions of (3)He particles with (192)Os. A production method involving high-current alpha-particle irradiation of enriched (192)Os and efficient chemical separation of radioplatinum was developed. Batch yields of about 1 MBq (195m)Pt and 8.7 MBq (193m)Pt were achieved. Compared to the reactor production these batch yields are very low, but the (192)Os(alpha,n)(195m)Pt and (192)Os(alpha,3n)(193m)Pt reactions are superior with respect to the specific activity of the products which is higher by two orders of magnitude.
Applied Radiation and Isotopes 04/2008; 66(4):545-51. · 1.17 Impact Factor
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ABSTRACT: Excitation functions for the formation of the arsenic radionuclides (71)As, (72)As, (73)As and (74)As in the interaction of protons with (nat)Ge were measured from the respective threshold energy up to 100 MeV. The conventional stacked-foil technique was used and the needed thin samples were prepared by sedimentation. Irradiations were done at three cyclotrons: CV 28 and injector of COSY at Forschungszentrum Jülich, and Separate Sector Cyclotron at iThemba LABS, Somerset West. The radioactivity was measured via high-resolution gamma-ray spectrometry. The measured cross section data were compared with the literature data as well as with the nuclear model calculations. In both cases, the results generally agree but there are discrepancies in some areas, the results of nuclear model calculation and some of the literature data being somewhat higher than our data. The integral yields of the four radionuclides were calculated from the measured excitation functions. The beta(+) emitting nuclide (72)As (T(1/2)=26.01 h) can be produced with reasonable radionuclidic purity ((71)As impurity: <10%) over the energy range E(p) = 18-->8 MeV; the yield of 93 MBq/microAh is, however, low. The radionuclide (73)As (T(1/2)=80.30 d), a potentially useful indicator in environmental studies, could be produced with good radionuclidic purity ((74)As impurity: <11%) over the energy range E(p) = 30 --> 18 MeV, provided, a decay time of about 60 days is allowed. Its yield would then correspond to 2.4 MBq/microAh, and GBq amounts could be produced when using a high current target.
Applied Radiation and Isotopes 10/2007; 65(9):1057-64. · 1.17 Impact Factor
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ABSTRACT: Excitation functions were measured by the stacked-foil technique for (nat)Rb(alpha,xn)(87m,87m+g,88)Y and (nat)Sr(alpha,xn)(86,88,89)Zr reactions from their respective thresholds up to 26 MeV. The samples for irradiation were prepared by sedimentation and pellet pressing techniques. The measured data were compared with those available in the literature. From the excitation functions, integral yields of the products were calculated. The suitable energy ranges for the production of (87)Y and (88)Y via (nat)Rb(alpha,xn) processes and of (89)Zr via the (nat)Sr(alpha,xn) process are E(alpha)=26-->20 MeV, E(alpha)=26-->5 MeV and E(alpha)=20-->8.5 MeV, respectively. The respective yields amount to 8.2, 0.08 and 0.9 MBq/microA h. Production of (88)Y is feasible if a waiting time of about 2 months is allowed to let the impurities decay out. Also, (87)Y can be produced with a relatively low impurity of (88)Y. The yields of both (88)Y and (87)Y via the present routes are, however, appreciably lower than those via the (nat)Sr(p,xn) processes. There is a possibility to produce (89)Zr via the alpha-particle irradiation of (nat)Sr. The yield is rather low but would be considerably increased if enriched (86)Sr would be used as target material. The radionuclidic impurity levels in all the three products are discussed.
Applied Radiation and Isotopes 05/2007; 65(5):561-8. · 1.17 Impact Factor
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ABSTRACT: The recently reported cross-section data for the production of 82Sr via the natRb(p,xn) 82Sr process were evaluated. For the natRb(p,xn) 85Sr process, cross-sections were measured experimentally over the proton energy range of 25-45 MeV, a region where very few data existed. An evaluation of the recently published data on the formation of 85Sr was then also performed. From the recommended data curves, the integral yields of the desired radionuclide 82Sr and the impurity 85Sr were calculated. Yields were also determined experimentally over several energy ranges using thick natRbCl targets. The experimental and calculated yields were found to be in agreement within 15%. These integral tests add confidence to the evaluated cross-section data. For the production of 82Sr, an incident proton energy of 60 MeV or above is recommended; the 85Sr impurity then corresponds to <20%.
Applied Radiation and Isotopes 02/2007; 65(2):247-52. · 1.17 Impact Factor
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ABSTRACT: The non-pure positron-emitting iodine isotope (120)I (T(1/2)=81 min) is a short-lived alternative to (124)I. (120)I has a positron abundance more than twice that of (124)I and a maximum positron energy of 4 MeV. This study was undertaken to evaluate and characterise the qualitative and quantitative PET imaging of (120)I.
(120)I was produced via the (120)Te(p,n) reaction on highly enriched (120)Te. The measurements were done with the Siemens scanner HR+ and the 2D PET scanner GE PC4096+. A cylinder containing three cold inserts and a phantom resembling a human brain slice were used to evaluate half-life, positron abundance and background correction. To analyse the image resolution, a -mm tube placed in water was filled with (120)I and (18)F. Comparisons with (18)F, (124)I and (123)I (measured with SPECT) were made using the Hoffman 3D brain phantom.
The half-life of 81.1 min was reproduced by the PET measurements. The PET-based positron abundance ranged from 47.9% to 55.0%. The reconstructed image resolution found with the HR+ was 5.4 mm FWHM (12.3 mm FWTM), in contrast to 4.6 mm (8.6 mm) when using (18)F. Erroneous positive and negative numbers of radioactivity found in the cold inserts became nearly zero when the background of gamma-coincidences was corrected for. Images of the Hoffman phantom were inferior to those obtained when (18)F or (124)I was applied but superior to the (123)I-SPECT images.
Our data show that (120)I of high radionuclidic purity can be regarded as a suitable nuclide for the PET imaging of radioiodine-labelled pharmaceuticals.
European journal of nuclear medicine and molecular imaging 12/2006; 33(11):1249-57. · 4.99 Impact Factor
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ABSTRACT: A comparative study of radioiodination of simple aromatic compounds using N-chlorosuccinimide (NCS), N-bromosuccinimide (NBS), N-chlorotetrafluoro-succinimide (NCTFS) and Chloramine-T (CAT) has been carried out in trifluoroacetic anhydride (TFAA) as an aprotic solvent. Optimization of the iodination procedure has been performed using anisole as the model substrate. A fast and simple “one-pot” synthesis via NCTFS, NCS or CAT leads to iodoanisoles with a radiochemical yield of about 70 %. For comparison, toluene and benzene have also been radioiodinated.
Journal of Labelled Compounds 07/2006; 19(7):807 - 819.
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ABSTRACT: A new method for practically carrier-free aromatic bromination has been developed using N-chloro-tetrafluoro-succinimide (NCTFS) and bromide-77. The optimum bromination conditions have been determined using toluene as a model system. In trifluoroacetic anhydride (TFA), which proved to be the best solvent, a “one-pot” synthesis with carrierfree bromide-77 gives rise to a 52 % radiochemical yield of bromotoluenes. No benzylbromide is formed. At room temperature the reaction is completed within about 30 min, the highest yields being obtained at NCTFS-concentrations of 2 · 10−2 mole/1. In pure anhydride (TFA) the chlorinating side-reaction of NCTFS does not take place. The reactivity towards simple benzene derivatives (C6H5X, X = OCH3, CH3, H, F, Br, NO2) is strongly dependent on the activation of the aromatic ring. A high ortho- and particularly para-selectivity is observed, and an electrophilic substitution process via ionic species is discussed.
Journal of Labelled Compounds 07/2006; 16(6):891 - 907.
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ABSTRACT: Nuclear data for production of the therapeutic radionuclides 32P, 64Cu, 67Cu, 89Sr, 90Y and 153Sm via (n,p) reactions on the target nuclei 32S, 64Zn, 67Zn, 89Y, (90)Zr and 153Eu, respectively, are discussed. The available information on each excitation function was analysed. From the recommended data set for each reaction the average integrated cross section for a standard 14 MeV d(Be) neutron field was deduced. The spectrum-averaged cross section was also measured experimentally. A comparison of the integrated value with the integral measurement served to validate the excitation function within about 15%. A fast neutron source appears to be much more effective than a fission reactor for production of the above-mentioned radionuclides in a no-carrier-added form via the (n,p) process. In particular, the possibility of production of high specific activity 153Sm is discussed.
Applied Radiation and Isotopes 07/2006; 64(6):717-24. · 1.17 Impact Factor
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ABSTRACT: Excitation functions of the reactions (nat)Sb((3)He,xn)(124,123,121)I were measured from their respective thresholds up to 35 MeV, with particular emphasis on data for the production of the medically important radionuclide (124)I. The conventional stacked-foil technique was used. From the experimental data the theoretical yields of the three investigated radionuclides were calculated. The yield of (124)I over the energy range E9(30He) = 35 --> 13 MeV amounts to 0.95 MBq/microA h. The radionuclidic impurities are discussed. A comparison of (3)He- and alpha-particle-induced reactions on antimony for production of (124)I is given. The alpha-particle-induced reaction on enriched (121)Sb and the (3)He-particle-induced reaction on enriched (123)Sb would lead to comparable (124)I yields, but the level of impurities in the latter case would be somewhat higher.
Applied Radiation and Isotopes 04/2006; 64(4):409-13. · 1.17 Impact Factor