Nuclear and chemical data for life sciences

Use of reactor produced radionuclides is popular in life sciences. However, cyclotron production of proton rich radionuclides are being more focused in recent times. These radionuclides have already gained attention in various fields, including life sciences, provided they are obtained in pure form. This article is a representative brief of our contributions in generating nuclear data for the production of proton rich radionuclides of terbium, astatine, technetium, ruthenium, cadmium, niobium, zirconium, rhenium, etc., which may have application in clinical, biological, agriculture studies or in basic research. The chemical data required to separate the product isotopes from the corresponding target matrix have been presented along with a few propositions of radiopharmaceuticals. It also emphasizes on the development of simple empirical technique, based on the nuclear reaction model analysis, to generate reliable nuclear data for the estimation of yield and angular distribution of emitted neutrons and light charged particles from light as well as heavy ion induced reactions on thick stopping targets. These data bear utmost important in radiation dosimetry.     

Production and separation of 111In: an important radionuclide in life sciences: a mini review

¹¹¹In is amongst the frequently used radionuclides in diagnostic nuclear medicine. Therefore its production and subsequent separation chemistry have been widely investigated since late 40s. ¹¹¹In is commonly produced in proton or α-particle induced reactions on cadmium or silver targets. However, in recent past, various heavy ion (⁷Li, ¹¹B, ¹²C etc.) activation routes have been proposed for its production. In this mini review, we have tried to portray the production routes of ¹¹¹In and chemical separation methodologies reported so far in the literature in a concise form. A critical analysis presented in this review will be helpful to select suitable nuclear reaction and radiochemical method to produce high purity ¹¹¹In for applications.     

Radiochemical separation and quality assessment for the <Superscript>68</Superscript>Zn target based <Superscript>64</Superscript>Cu radioisotope production

The radiochemical separation of the different radionuclides (⁶⁴Cu, ⁶⁷Cu, ⁶⁷Ga, ⁶⁶Ga, ⁵⁶Ni, ⁵⁷Ni, ⁵⁵Co, ⁵⁶Co, ⁵⁷Co, ⁶⁵Zn, ¹⁹⁶Au) induced in the Ni supported Cu substrate — ⁶⁸Zn target system, which was bombarded with the 29.0 MeV proton beam, was performed by ion-exchange chromatography using successive isocratic and/or concentration gradient elution techniques. The overlapped gamma-ray spectrum analysis method was developed to assess the ⁶⁷Ga and ⁶⁷Cu content in the ⁶⁴Cu product and even in the post-⁶⁷Ga production ⁶⁸Zn target solution without the support of radiochemical separation. This method was used for the assessment of ⁶⁴⁺⁶⁷Cu radioisotope separation from ⁶⁷Ga, the quality control of ⁶⁴Cu product and the determination of the ⁶⁸Zn (p,2p)⁶⁷Cu reaction yield. The improvement in the targetry and the optimization of proton beam energy for the ⁶⁸Zn target based ⁶⁴Cu and ⁶⁷Ga production were proposed based on the stopping power and range of the incident proton and on the excitation functions, reaction yields and different radionuclides induced in the target system.     

Proton activation analysis for chromium,nickel and copper

Proton activation analysis has been applied to develop a procedure for the simultaneous determination of chromium, nickel and copper. The procedure involves the bombardment of the sample with protons to induce⁵²Cr(p, n)^52mMn,⁶⁰Ni(p, n)⁶⁰Cu and⁶³Cu(p, n)⁶³Zn reactions. These reactions have been studied for proton energies from 11 MeV to 15 MeV. Thick target yields for the production of the indicator radionuclides as well as the sensitivities of the determination have been measured in this energy region and are compared with results obtained for other charged particle induced reactions. Detailed data are given on nuclear and instrumental interferences. The trace elements have been determined nondestructively and simultaneously in cobalt with a relative precision of 8 to 15%.     

The ISOLPHARM project: ISOL-based production of radionuclides for medical applications

Radionuclides for radiopharmaceuticals can be produced in cyclotrons or nuclear reactors. Each of these production modes has serious issues, such as high target costs, production of long-lived wastes and contaminants, expensive separation. For this reason, new methods are under consideration for the production of highly pure radionuclides. The ISOL (Isotope Separation On-Line) method is the major technique for the production of radioactive ion beams for nuclear physics applications. The SPES-ISOLPHARM project at INFN-LNL (Istituto Nazionale di Fisica Nucleare-Laboratori Nazionali di Legnaro) is a feasibility study for the production of medical isotopes exploiting the ISOL method. The ongoing activities concerning a recent experiment focused on ¹¹¹Ag, a study performed in collaboration with Padova and Trento Universities, is presented.

     

Comparison on the production of radionuclides in 1.4 GeV proton irradiated LBE targets of different thickness

This is the first report on the inventory of radionuclides produced in 1.4 GeV proton induced reaction on Lead–Bismuth Eutectic (LBE) targets. LBE targets of 6 mm diameter and 1 to 8 mm lengths were irradiated with 1.4 GeV protons. The radionuclides ranging from ⁷Be (53.12 days) to ²⁰⁷Po (5.8 h) were identified in the samples with the help of time resolved γ-ray spectroscopy. However, there is no signature of formation of At radioisotopes, which can be produced by the interaction of secondary particles, typical for thick targets.     

Cross-section calculations of proton induced (p,n) and (p,2n) reactions for production of diagnostic 67Ga, 81Rb, 111In, 123,124I, 123Cs and 123Xe radioisotopes

Investigation of pre-equilibrium (PEQ) and equilibrium (EQ) effects on proton induced reactions for production of radioisotopes are very important. Therefore, in this study, we have calculated the PEQ and EQ cross-sections for ⁶⁷Zn(p,n)⁶⁷Ga, ⁶⁸Zn(p,2n)⁶⁷Ga, ⁸²Kr(p,2n)⁸¹Rb, ¹¹¹Cd(p,n)¹¹¹In, ¹¹²Cd(p,2n)¹¹¹In, ¹²³Te(p,n)¹²³I, ¹²⁴Te(p,2n)¹²³I, ¹²⁴Te(p,n)¹²⁴I and ¹²⁴Xe(p,2n)¹²³Cs reactions for production diagnostic radioisotopes. Calculations have been performed by using the hybrid model, geometry dependent hybrid model and full exciton model of PEQ reaction mechanism with 1–40 MeV proton incident energy. We have also investigated the EQ effects on these reactions using the Weisskopf–Ewing model in the same energy range. The excitation functions including the PEQ and EQ effects on these reactions are evaluated by using the ALICE/ASH (2006) and the TALYS 1.4 (2011) codes. Our results have shown that using these codes is suitable for production diagnostic isotopes mentioned above. To obtain excitation functions for producing the diagnostic radioisotopes the PEQ mechanism has been found more dominant than that of the EQ. The results are discussed and compared with the available experimental data.     

Implantation assisted deposition of hard carbon coatings on steel substrates

Summary Rutherford backscattering in combination with ¹²C(d,p_o) ¹³C nuclear reaction has been applied to understand the high wear resistance of tool steel after implantation of carbon ions. Slant deuteron incidence and glancing proton detection enables the called nuclear reaction for carbon depth profiling within a 200 nm thick near surface layer structure. Carbon ion beam assisted deposition of carbon together with carbon/substrate ion beam mixing was observed.     

New developments in the production of theranostic pairs of radionuclides

A brief historical background of the development of the theranostic approach in nuclear medicine is given and seven theranostic pairs of radionuclides, namely ^44gSc/⁴⁷Sc, ⁶⁴Cu/⁶⁷Cu, ⁸³Sr/⁸⁹Sr, ⁸⁶Y/⁹⁰Y, ¹²⁴I/¹³¹I, ¹⁵²Tb/¹⁶¹Tb and ¹⁵²Tb/¹⁴⁹Tb, are considered. The first six pairs consist of a positron and a β^?-emitter whereas the seventh pair consists of a positron and an α-particle emitter. The decay properties of all those radionuclides are briefly mentioned and their production methodologies are discussed. The positron emitters ⁶⁴Cu, ⁸⁶Y and ¹²⁴I are commonly produced in sufficient quantities via the (p,n) reaction on the respective highly enriched target isotope. A clinical scale production of the positron emitter ^44gSc has been achieved via the generator route as well as via the (p,n) reaction, but further development work is necessary. The positron emitters ⁸³Sr and ¹⁵²Tb are under development. Among the therapeutic radionuclides, ⁸⁹Sr, ⁹⁰Y and ¹³¹I are commercially available and ¹⁶¹Tb can also be produced in sufficient quantity at a nuclear reactor. Great efforts are presently underway to produce ⁴⁷Sc and ⁶⁷Cu via neutron, photon and charged particle induced reactions. The radionuclide ¹⁴⁹Tb is unique because it is an α-particle emitter. The present method of production of ¹⁵²Tb and ¹⁴⁹Tb involves the use of the spallation process in combination with an on-line mass separator. The role of some emerging irradiation facilities in the production of special radionuclides is discussed.     

Excitation functions of proton induced nuclear reactions on natural tellurium up to 18 MeV for validation of isotopic cross sections

Summary Excitation functions of proton induced nuclear reactions on natural Te were investigated up to 18 MeV. Cross sections for production of ^{121,123,124,126,128,130g}I and ^121gTe were measured. The new experimental data were compared with the results of ALICE-IPPE model calculations and with data found in the literature and measured on natural or enriched Te targets. The new data can be effectively used for validation of recommended cross sections of medically relevant ¹²³I and ¹²⁴I.     

Studies in heavy ion activation analysis trace determination possibilities with9Be bombardment

⁹Be induced radioactivation was used to study the trace determination of 19 elements at 3 different ion beam energies (E_lab=14, 32 and 63 MeV⁹Be²⁺). Nine nuclear reactions, yielding radionuclides with half-lives longer than 2.5 m, present potential analytical features. Beside the very sensitive detection of B and N, the multielemental determination of Na, Si, Ca, Sc, and Zn is possible with a⁹Be ion beam of appropriate incident energy. Nuclear interferences have also been investigated and quantified.     

Evaporation behavior of water and concentration of technetium and rhenium using thin film evaporator

The nuclear energy cycle requires the recycling of nuclear fuel, water, chemical reagents, and the volume reduction of radioactive liquid wastes. A fundamental technique for continuous recovery of water using a thin-film evaporator was examined. Appropriate recovery measurements were: an evaporator heat temperature of 323 K, a feed rate of 0.23 cm³s⁻¹, a vacuum pressure of 15 mmHg (2 kPa), and impeller rotational speeds of 500–600 rpm (min⁻¹). The concentration of trace technetium and rhenium in aqueous solutions was also studied. A decontamination factor of 10⁵ for rhenium was obtained.     

Experimental Simulation on Separation of Alpha-Particle Induced Rhenium Isotopes from Bulk Tantalum

Trace level tantalum and rhenium, ¹⁸²Ta and ^186,188Re, have been separated with liquid anion exchanger, TOA from HNO₃ medium. The feasibility of the separation process has also been verified for the separation of trace level rhenium from bulk or macro quantity of tantalum. The developed radiochemical scheme will be useful for the separation of carrier-free rhenium radionuclides produced in -particle activated matrix target.     

A novel technique for simultaneous diagnosis and radioprotection by radioactive cerium oxide nanoparticles: study of cyclotron production of <Superscript>137m</Superscript>Ce

Application of nanoparticles in nuclear medicine has aimed to develop diagnosis and therapeutic techniques. Cerium oxide nanoparticles (CNPs) are expected to be useful for protection of healthy tissue from radiation-induced harm and could serve therapeutic function. Among a variety of cerium radioisotopes, ^137mCe (T _1/2 = 34.4 h, IT (99.22%), β⁺ (0.779%)) could be a novel candidate radionuclide in the field of diagnosis owing to its appropriate half-life, 99.91% natural abundance of target and its intense gamma line at 254.29 keV. In this study, ^137mCe excitation function via the ^natLa(p,3n) reaction was calculated by TALYS-1.2 and EMPIRE-3 codes. The excitation function calculations demonstrated that the ^natLa(p,3n)^137mCe reaction leads to the formation of the ^136/138Ce isotopic contamination in the 22–35 MeV energy range. Interestingly, the isotopic impurities of ^137mCe could serve radio protector function. Overall results indicate that the cyclotron produced ^137mCeO₂ nanoparticles by irradiation of a target encompassing lanthanum oxide nanoparticles could be a potent alternative for conventional diagnostic radionuclides with simultaneous radioprotection capacity.     

Occurrence of natural radionuclides and fallout cesium-137 in dry-season agricultural land of South Western Nigeria

The radioactivity of the Opa river — irrigated farmlands in the south western Nigeria was determined using an HpGe based, low-level passive gamma-counting system. With the exception of two isotopes, the main radionuclides analysed in the sample were the progenies of²³⁸U and²³²Th. The other two isotopes were the naturally occurring⁴⁰K and the anthropogenic¹³⁷Cs. The result obtained showed elevated levels of radioactivity from all detected radionuclides compared to the published data for this area. Enhanced levels of naturally occurring radionuclides is attributed to the use of phosphatic fertilizers for dry season vegetable cultivation along this river banks. The presence of the fission product¹³⁷Cs could be traced to the fallouts occasioned by the various French nuclear tests in the Sahara desert, and probably, some effect of the more recent nuclear reactor accident at Chernobyl in 1986.     

Activation rates and chemical recovery of67Cu produced with low energy proton irradiation of enriched70Zn targets

Copper-67 is a radioisotope with significant potential for diagnostic and therapeutic applications in nuclear medicine. Despite its promise,⁶⁷Cu has failed to make an impact in clinical nuclear medicine, primarily because it is available sporadically, and in limited quantities. Common methods of production rely on high energy proton irradiation of natural zinc targets or on induced reactions using high energy neutrons at nuclear reactors. We have evaluated alternative production methods that could provide year-round adequate supply of this isotope. Using a low energy accelerator, we have studied the production of⁶⁷Cu by proton reactions on enriched⁷⁰Zn. Our results indicate that it is possible to produce useful quantities of⁶⁷Cu from the irradiation of enriched⁷⁰Zn with protons that have energies of less than 20 MeV. Production rates are higher than currently used methods at high energy accelerators or reactors. This isotope can be made available throughout the year as a result of this research.     

Nuclear model calculation for cyclotron production of 61Cu as a PET imaging

⁶¹Cu is positron emitter and can be used as the PET and molecular imaging. In this study cyclotron production of ⁶¹Cu via ⁶¹Ni(p,n)⁶¹Cu, ^natNi(p,x)⁶¹Cu, ^natNi(d,x)⁶¹Cu, ^natNi(α,x)⁶¹Cu, ^natZn(p,x)⁶¹Cu and ⁵⁹Co(α,2n)⁶¹Cu reactions was investigated. The ALICE/ASH (hybrid and GDH models) and TALYS-1.2 codes were used to calculate excitation functions for proton, alpha and deuteron induced on ^natNi, proton on ⁶¹Ni and ^natZn and also alpha-particle on ⁵⁹Co targets that lead to the production of ⁶¹Cu radioisotopes using intermediate energy accelerators. In addition, we compared the data obtained from in this study with the reported measurement by experimental data. Moreover, optimal thickness of the targets and physical yield were obtained by stopping and range of ions in matter code for each reaction. Eventually ⁶¹Ni(p,n)⁶¹Cu and ⁵⁹Co(α,2n)⁶¹Cu reaction to produce ⁶¹Cu in no-carrier added state with high production yield was suggested. Finally the ^natNi(p,x)⁶¹Cu reaction was employed to test the target preparation using electroplating technique.     

Field testing of collection and measurement of radioxenon for the Comprehensive Test Ban Treaty

Pacific Northwest National Laboratory, with guidance and support from the U.S. Department of Energy's NN-20 Comprehensive Test Ban Treaty (CTBT) Research and Development program, has developed and demonstrated a fully automatic sampler-analyzer (ARSA) for the collection and quantitative measurement of the four xenon radionuclides,^131mXe (11.9 d),^133mXe (2.19 d),¹³³Xe (5.24 d), and¹³⁵Xe (9.10 h), in the atmosphere. These radionuclides are important signatures in monitoring for compliance to a CTBT, and may have applications in stack monitoring and other areas where xenon radionuclides are present. The activity ratios between certain of these radionuclides permit discrimination between radioxenon originating from nuclear detonations and that from nuclear reactor operations, nuclear fuel reprocessing, or from medical isotope production and usage. With the ARSA system, xenon is continuously and automatically separated from the atmosphere at flow rates of about 100 lpm by sorption-bed techniques. Samples collected in 8 hours are automatically analyzed by electron-photon coincidence spectrometry to provide detection sensitivities as low as 100 μBq/m³ of air. This sensitivity is about 10-fold better than achieved with reported laboratory-based procedures¹ for the short time collection intervals of interest. Gamma-ray energy spectra and gas analysis data are automatically collected.