Physical optimization of production by deuteron irradiation of high specific activity (177g)Lu suitable for radioimmunotherapy.

Deuteron-induced nuclear reactions for generation of no-carrier-added (NCA) Lu isotopes were investigated using the stacked-foil activation technique on natural Yb targets at energies up to Ed=18.18MeV. The decay curve of ¹77Yb, the growth curve of the cumulative (direct and indirect) and the direct production of (177g)Lu were determined. The analysis of these curves conducts to the evidence that the predominant route for the production of (177g)Lu is the indirect reaction ¹76Yb(d,p)¹77Yb, which decays to (177g)Lu. In the spectra acquired one year from the EOB the γ lines of (177m)Lu are not evident. A comparison between the calculated activity of (177g)Lu produced with a cyclotron and with a nuclear reactor is given.

Excitation function for deuteron induced nuclear reactions on natural ytterbium for production of high specific activity 177g Lu in no-carrier-added form for metabolic radiotherapy.

Deuteron-induced nuclear reactions for generation of no-carrier-added Lu radionuclides were investigated using the stacked-foil activation technique on natural Yb targets at energies up to E(d)=18.18 MeV. Excitation functions of the reactions (nat)Yb(d,xn)(169,170,171,172,173,174g,174m,176m,177g)Lu and (nat)Yb(d,pxn)(169,175,177)Yb have been measured, among them three ((169)Lu, (174m)Lu and (176m)Lu) are reported for the first time. The upper limit of the contamination from the long-lived metastable level (177m)Lu was evaluated too. Thick-target yields for all investigated radionuclides are calculated.

Rapid determination of (90)Sr impurities in freshly "generator eluted"(90)Y for radiopharmaceutical preparation.

(90)Y is one of the most useful radionuclides for radioimmunotherapeutic applications and has a half-life (t(1/2)=64.14h) suitable for most therapeutic applications, beta particles of high energy and decays to a stable daughter. It is significant that (90)Y is available conveniently and inexpensively from a radionuclide "generator" by decay of its parent, (90)Sr. Nevertheless, current and planned clinical applications with [(90)Y] labelled compounds employ activity levels that cannot be readily obtained from an in-house generator, but from commercial sources. We have evaluated Eichrom's Sr-resin, either as an "in-house" generator or as a fast QC method for analysis of (90)Y solutions. In particular, for the development as a generator, we investigated the percentage of the radio-Sr in the first 8M HNO(3) eluate: in this fraction the concentration of (90)Sr must be smaller than 10(-5)% (recommendations of the International Commission on Radiological Protection). For evaluation as a rapid QC method, we analyzed the concentration of (90)Y in all the fractions containing "only" radio-Sr: (90)Y should not be present in these eluates. After the collection of beta(-) and gamma spectra and analysis of them, we concluded that commercial Sr-resin minicolumn cannot give us the results expected; we developed an in-house system loaded with 4mL of Sr-resin which gave better results as a generator and a rapid QC method.

On the photon self-absorption correction for thin-target-yields vs. thick-target-yields in radionuclide production.

In the experimental determination of activity of low gamma energy emitters by HPGe spectrometry, after cyclotron irradiation of thick targets of high Z elements, it is mandatory to introduce a correction for gamma-ray self-absorption in the target. The amount of this correction is substantial in order to provide a statistically acceptable agreement with the thick-target-yield data obtained by integration of the experimental thin-target-yield data that are very slightly affected by self-absorption instead.

Improved determination of the position and activity of a radioactive point source inside a bulky medium using several detectors. The special case of a lung counter--a general view.

A method is described to locate a radioactive point source in a lung using a commercial array of lung detectors. The method takes advantage of the fact that modern commercial systems consist of several Ge detectors, each connected to a multi-channel analyzer, and the information from each detector can be analyzed separately. The system is calibrated with point sources placed in various locations in the lungs of a phantom. A vector method is presented for determining which of the calibration locations in the phantom is closest to the location of the unknown point source. It has been shown that the accuracy of the method increases with increasing number of the vector dimensions. A higher dimensionality can be achieved by analyzing counts of several gamma lines or by using more detectors.

On the "artificial" nature of Tc and the "carrier-free" nature of 99mTc from 99Mo/99mTc generators.

Two widespread misconceptions regarding Tc are dealt with. First, it is shown that although primordial Tc has decayed completely, Tc is still present in nature due to natural processes, in addition to substantial man-made quantities. Thus, Tc cannot be considered as a purely artificial element. Second, it is shown that (99m)Tc from (99)Mo/(99m)Tc generators is certainly not carrier-free (CF) and that, "no-carrier-added" (NCA) is a more appropriate designation. As a quantitative measure of the amount of long-lived (99g)Tc carrier present in (99m)Tc preparations from generators, the Isotope Dilution Factor (IDF) is used and calculated for some practical situations.

Preparation of "high specific activity" radiochemical forms of vanadium, manganese and thallium for metallo-toxicological studies.

In this paper are presented the production methods for very "high specific activity" radionuclides (HSA-RN) of vanadium, manganese and thallium which have been developed in our laboratories for labelling different chemical forms of these elements present in the echo-systems in ultra-trace amounts, for metallo-toxicological and bio-kinetic studies. Use was made of both cyclotron and thermal nuclear reactor. If the nuclear reaction product has atomic number different from irradiated target, it is possible separating the radioactive nuclide from irradiated target, without addition of isotopic carrier. This kind of radionuclide is named No Carrier Added, NCA, and his specific activity, As is very high and can reach values close to the theoretical Carrier Free one, CF. The experimental determination of specific activity, chemical and radiochemical purities is mandatory for all these kinds of applications.

"High specific activity" radiotracers for metallo-toxicological studies: cyclotron and nuclear reactor production, radiochemical separation and "quality control": platinum, iridium, gold, copper and gallium.

Very High Specific Activity RadioNuclides, HSARN, are a powerful tool to label a wide variety of chemical elements and compounds present in the biosphere in ultra-trace amounts. Medium and high Z radionuclides, can be produced by irradiation in light-ions accelerator and sometimes nuclear reactor. If the nuclear reaction product has atomic number different from irradiated target, it is possible separating the radioactive nuclide from irradiated target, without addition of isotopic carrier. These kinds of radionuclides are named No Carrier Added, NCA, and their specific activity is very high and can reach values close to the theoretical Carrier Free one. The true specific activity must be determined by use of very sensitive radioanalytical techniques. If a low isotopic dilution factor is obtained, these radiotracers are used to label inorganic species and complexes of elements, which are presently introduced into the echo-systems by human activities. New production methods for NCA Pt, Ir, Au, Cu and Ga radiotracers are presented, with some details on radiochemistry and quality controls.

Thin-target excitation functions, cross-sections and optimised thick-target yields for natMo(p,xn)(94g ,95m,95g,96(m + g))Tc nuclear reactions induced by protons from threshold up to 44 MeV. No Carrier Added radiochemical separation and quality control.

This work describes the method adopted in our laboratories, to produce 94gTc, 95gTc, 95mTc and 96gTc radionuclides via proton-cyclotron irradiation on molybdenum targets of natural isotopic composition. A new set of experimental thin-target excitation functions and "effective" cross-sections for direct natMo(p,xn)(A)Tc [with A = 94, 95, 95, 96] nuclear reactions, with incident proton energy in the range from threshold up to 44 MeV is presented. Some definitions of the equations used and nuclear data traceability are reported. Thick-target yield values were calculated and optimised, by numerical fitting and integration of the measured excitation functions. These values allow optimisation of production yield of one radionuclide, minimising at the same time the yield of the others. Radiochemical separation on NCA technetium radionuclides from both molybdenum target and niobium, zirconium and yttrium radioactive by-products is reported. Quality control tests of the radiotracers were developed for the applications envisaged in environmental metallo-biochemical toxicology.

A rapid improved method for gamma-spectrometric determination of 202Tl impurities in [201Tl]-labelled radiopharmaceuticals.

Despite the cyclotron production method and the efficiency of the radiochemical procedures adopted, the long-lived radio-isotopic impurity 202Tl is always present in [201Tl]-labelled radio-pharmaceuticals, together with other short-lived impurities like, 200Tl. Rapid determination of the 202Tl impurity, can be achieved using HPGe gamma spectrometry and a detector shielded by a 5 mm thick envelope of lead. In this way, dead-time correction errors, Compton and X-ray background, are very efficiently avoided and suppressed. The same method could be applied routinely in nuclear medicine, to determine the radioisotopic purity of 201Tl by means of an ionisation chamber dose calibrator.