TENDL-2017 Library Research Articles

Theoretical models validation of Cr -51 production reactions for medical applications

This study provides a thorough simulation and analysis of cross-sections for the production of 51Cr by various nuclear reactions. Our objective is to validate the production process of 51Cr, an essential radionuclide used in nuclear medicine for studying blood cells’ physiological and pathological characteristics. In order to do this, we used the nuclear level density, optical model potential, and preequilibrium model integrated into the TALYS 1.96 code for theoretical modeling. The obtained results have been compared with experimental data taken from the EXFOR database. We have also taken TENDL library data and TALYS as a whole code to enhance our evaluation. The study assesses multiple nuclear reactions: 51V(p,n)51Cr, 51V(d,2n)51Cr, 48Ti(a,n)51Cr, 52Cr(n,2n)51Cr, 54Fe(n,a)51Cr, and 55Mn(p,x)51Cr in order to identify the most effective routes in terms of production, relative variance analysis, presence of nuclidic impurities, and the optimum energy range. The cross-section, theoretical yield, target thickness, and activity have been calculated to optimize and help in finding the best reaction conditions, which improve the production of 51Cr inside a cyclotron for medical uses.

Activation analysis of RFT-30 cyclotron target assembly

This work evaluated the validity of computer simulation codes by comparing the results of an inventory calculation for a89Zr target assembly with measured data obtained using a high-purity germanium detector. For the inventory calculation, the MCNP6 and FISAPCT-Ⅱ codes were used, and for the measurement, efficiency derived from the efficiency transfer method was used. The MCNP6's ENDF/B-Ⅶ library (TENDL-2017 library for 89Y) and the CEM03.03 physics model were employed to simulate proton reactions, while the ENDF/B-Ⅶ library alone was utilized for neutron reactions. To verify the efficiency obtained by the efficiency transfer method, the calculated activity of the reference sources was compared with the measured activity and confirmed to be within 11%. For the target assembly, the average calculated-to-measured activity (C/M) ratio was determined to be 0.7–2.0 (physics model) and 0.7–1.5 (data library with TENDL), thus confirming the validity of the computer simulation codes. The above results suggest that the methods presented in this study could be used to establish decommissioning plans for the cyclotron facility, including plans for waste disposal of cyclotron components such as target assemblies.

Excitation functions and isomeric cross-section ratios of (d,xn) reactions on 86\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{86}$$\\end{document}Sr

Excitation functions of the 86\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{86}$$\\end{document}Sr(d,n)87m,87g\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{87m,87g}$$\\end{document}Y, 86\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{86}$$\\end{document}Sr(d,2n)86m,86g\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{86m,86g}$$\\end{document}Y and 86\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{86}$$\\end{document}Sr(d,3n)85m,85g\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{85m,85g}$$\\end{document}Y reactions on enriched 86\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{86}$$\\end{document}Sr target were measured by the activation technique up to deuteron energies of 49 MeV. The isomeric cross-section ratios as a function of projectile energy were deduced from the measured data for 87m\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{87m}$$\\end{document}Y, 87g\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{87g}$$\\end{document}Y(cum), 86m\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{86m}$$\\end{document}Y, 86g\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{86g}$$\\end{document}Y(cum), 85m\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{85m}$$\\end{document}Y and 85g\\documentclass[12pt]{minimal} \\usepackage{amsmath} \\usepackage{wasysym} \\usepackage{amsfonts} \\usepackage{amssymb} \\usepackage{amsbsy} \\usepackage{mathrsfs} \\usepackage{upgreek} \\setlength{\\oddsidemargin}{-69pt} \\begin{document}$$^{85g}$$\\end{document}Y pairs for the same energy range. All measurements are reported for the first time. The experimental data were compared with the data from the TENDL library which is based on TALYS calculation with default parameters. No satisfactory agreement was observed. Nuclear model calculations were then performed using the codes TALYS and EMPIRE with some parameter adjustments, and compared with the experimental data. The quality of the agreement between experimental data and model calculations was numerically quantified. In general, the data as well as the isomeric cross-section ratios are partially reproduced by the model calculations, provided the input model parameters are properly chosen and the level structure of the product nucleus is thoughtfully considered.

Activation cross sections of alpha-particle-induced reactions on natural lanthanum up to 50 MeV

We performed experiments to measure the activation cross sections of α-particle-induced reactions on natLa up to 50 MeV. The production cross sections of the medical radionuclide 142gPr and simultaneously formed 139,138mPr, and 141,139gCe were obtained. The stacked-foil activation method and the high-resolution γ-ray spectrometry were employed for the measurements. The results were compared with previous experimental data and theoretical values deduced by TALYS (TENDL library). The production cross section data for 139gCe and 138mPr were determined for the first time.

Study of activation cross sections of proton induced reactions on natBa and natCe near their threshold energy regions

Abstract Activation cross-sections of the nuclear reactions natBa(p,x)135,132gLa, 135mBa and natCe(p,x)142,139,138mPr, 141,139,137mCe have been measured experimentally at the MGC-20 cyclotron, Cairo, Egypt, from their respective threshold energies up to about 14.7 MeV. Stacked foil irradiation technique and high-resolution gamma-ray spectroscopy were used. A comparison between the experimental and theoretical data derived from the nuclear model codes EMPIRE and TALYS (in the form of the TENDL library) was performed. The agreement in the low-energy region is fairly good. Integral yields of the produced radioisotopes were estimated from the present cross-section data and the results are discussed in terms of their production possibilities.

Indirect measurement of the(n,γ)Sb127cross section

Nuclei in the $^{135}$I region have been identified as being a possible bottleneck for the \textit{i} process. Here we present an indirect measurement for the Maxwellian-averaged cross section of $^{126}\text{Sb}(n,\gamma)$. The nuclear level density and the $\gamma$-ray strength function of $^{127}$Sb have been extracted from $^{124}$Sn$(\alpha,p\gamma)^{127}$Sb data using the Oslo method. The level density in the low-excitation-energy region agrees well with known discrete levels, and the higher-excitation-energy region follows an exponential curve compatible with the constant-temperature model. The strength function between $E_\gamma\approx$ 1.5-8.0 MeV presents several features, such as an upbend and a possibly double-peaked pygmy-like structure. None of the theoretical models included in the nuclear reaction code TALYS seem to reproduce the experimental data. The Maxwellian-averaged cross section for the $^{126}$Sb$(n,\gamma)^{127}$Sb reaction has been experimentally constrained by using our level-density and strength-function data as input to TALYS. We observe a good agreement with the JINA REACLIB, TENDL, and BRUSLIB libraries, while the ENDF/B-VIII.0 library predicts a significantly higher rate than our results.

Theoretical cross-sections of deuteron-induced reaction on natural chromium by EMPIRE code for the production of 52Mn, 54Mn, 51Cr and 48V

Manganese-52 ground (52gMn) is a positron emitter and its beneficial properties make it a strong candidate for positron emission tomography (PET) imaging. Furthermore, the PET isotope 52gMn has been proposed as a suitable candidate for combination with proteins and antibodies. Moreover, Mn2+ has a paramagnetic property, thus the Mn isotope is ideal for use in bimodal PET/magnetic resonance (MR) images as a traceable nuclide, that can provide anatomical, molecular and physiological information of tissues. In this work, the theoretical calculation of the cross-section to produce 52Mn based on EMPIRE 3.2.2 code was carried out, focusing the attention on the optimization of the code parameters. The calculated cross-sections, obtained considering the effect of different level density models of the code, were compared with the experimental ones, to produce 52Mn isotopes by deuteron beam irradiation in the energy range up to 35 MeV on natCr target. At the same time, the co-produced 54Mn, 51Cr and 48V from natCr(d,X) nuclear reactions have been investigated. The results are also compared with the data taken from the online TENDL library of different versions.

Evaluation of cross-section data for radionuclides used in positron emission tomography by effects of level density models using EMPIRE 3.2.2 code

This work presents the evaluated results of cross-sections for natural chromium (natCr) with several nuclear reactions of natCr(d,x)52g,m+Mn, natCr(d,x)54Mn, natCr(d,x)51Cr, and natCr(d,x)48V using the statistical nuclear model EMPIRE 3.2.2 code with different level density models, for some radionuclides used in positron emission tomography. We compared the results to data sets found in literature, and data chosen from various sets of the electronic TENDL library.

Determination of lattice physics properties and uncertainties in a solid fuel molten salt cooled assembly using OpenMC

The desire for reducing our carbon footprint is driving significant interest in advanced nuclear reactors to produce energy. One promising technology is the Fluoride Salt-Cooled High-Temperature Reactor (FHR) which provides both electricity and high temperatures for use in process heat applications. The reactor technology considered in this work is a Generation IV design that uses TRISO particles uniformly embedded in fuel stripes within the fuel plates and liquid salt as coolant. The fuel design and conditions are the same as those used in a recent OECD/NEA FHR Benchmark. This paper reports the multiplication factor, fission reaction rate, and neutron spectrum for different cases from that benchmark study. A unique contribution of this work is the assessment of nuclear data uncertainty impact on the Figures of Merit used in the FHR benchmark. The OpenMC Monte Carlo code and perturbed nuclear data files from the TENDL-2017 library were utilized in these analyses. This work is part of the ongoing international efforts to explore and identify the applicability of current methods and codes for FHR simulations and molten salt reactors in general.

Production cross section measurements of proton-induced reactions on Nb at energies of 58 to 100 MeV

Production cross sections for the $^{93}\mathrm{Nb}(p,x)^{90}\mathrm{Mo},\phantom{\rule{0.28em}{0ex}}^{92m,90,89m}\mathrm{Nb},\phantom{\rule{0.28em}{0ex}}^{89,88,86}\mathrm{Zr}$, and $^{88,87m,87g}\mathrm{Y}$ reactions were measured using a stacked-foil technique in the proton energy range of 58--100 MeV. The target was arranged in the stack including Nb, Al, Au foils, and Pb plates and was irradiated with 100-MeV protons. After the irradiation, the production yields of the interested radionuclei were measured by a $\ensuremath{\gamma}$-ray spectroscopy system using HPGe detectors. Proton beam intensities were measured using the $^{27}\mathrm{Al}(p,3pn)^{24}\mathrm{Na},\phantom{\rule{0.28em}{0ex}}^{197}\mathrm{Au}(p,p3n)^{194}\mathrm{Au}$, and $^{197}\mathrm{Au}(p,pn)^{196}\mathrm{Au}$ monitor reactions. Some 54 cross section data points were measured, including independent and cumulative cross sections and were compared with other experimental data. The excitation functions of the reactions were also calculated by nuclear models using the talys code with a default mode as well as different nuclear level-density models. The calculated cross sections were compared to the measured data and to the tendl library. It was figured out that the theoretical calculations could reproduce the shape of the measured cross sections well, whereas the magnitude of the cross sections was not reproduced. It was also shown that the preequilibrium mechanism played an important role in the cross section calculations in this paper.

Upgrade of IAEA recommended data of selected nuclear reactions for production of PET and SPECT isotopes

An IAEA research project was dedicated to the compilation, evaluation and recommendation of cross-section data for the accelerator production of 11C, 13N, 15O, 18F, 64Cu, and 124I positron-emitting radionuclides clinically used for PET imaging, and for the accelerator production of two gamma emitters, 81Rb and 123I, used in SPECT imaging. Cross sections for 19 charged-particle induced reactions that can be employed for radionuclide accelerator production were evaluated including uncertainties. The resulting reference cross-section data were obtained from Padé fits to selected and corrected experimental data, and integral thick target yields were subsequently deduced. Uncertainties in the fitted results were estimated via a Padé least-squares method with the addition of a 4% assessed systematic uncertainty to the estimated experimental uncertainty. Experimental data were also compared with comprehensive predictions available from the TENDL library that reflects the current status of theoretical modelling. All of the numerical reference cross-section data with their corresponding uncertainties and deduced integral thick target yields are available on-line at the IAEA-NDS medical portal www-nds.iaea.org/medportal/ and also at the IAEA-NDS web page www-nds.iaea.org/medical/.

Measurement of very high threshold reactions using 252Cf source

Only neutron spectrum standard is 252Cf spontaneous fission neutron spectrum. However, the high energy tail of this spectrum is loaded with high uncertainty. To reduce this uncertainty, it is crucial to use validated cross sections with low uncertainty. The explored set of reactions covers 58Ni(n,X)57Co, 169Tm(n,3n)167Tm, 197Au(n,3n)195Au, 209Bi(n,3n)207Bi and 209Bi(n,4n)206Bi threshold reactions. Measurement of dosimetric 169Tm(n,3n)167Tm, 209Bi(n,3n)207Bi and 209Bi(n,4n)206Bi reactions spectral averaged cross sections (SACS) is included in NEA's High Priority Nuclear Data Request List. All these reactions SACS were measured for the first time. All SACS were derived from experimentally determined reaction rates by gamma spectrometry using the same high-purity germanium detector. In the case of 169Tm(n,3n)167Tm reaction, the difference between experimental and calculated value using the IRDFF-II library is only 1.45%. Concerning 197Au(n,3n)195Au reaction, the reasonable agreement is achieved only using the TENDL-2017 library. In the case of 209Bi(n,3n)207Bi reaction, agreement within uncertainty is not achieved with any library unlike 209Bi(n,4n)206Bi reaction where the agreement within uncertainty is achieved with IRDFF-II library. The best agreement for 58Ni(n,X)57Co reaction is achieved using ENDF/B-VIII library.

Activation cross section measurement of the deuteron-induced reaction on yttrium-89 for zirconium-89 production

Activation cross sections of the deuteron-induced reactions on 89Y were measured up to 24 MeV deuteron energy. The experiment was performed at the RIKEN AVF cyclotron. Excitation functions of the reactions 89Y(d,x)88,89Zr, 88,90mY, 87mSr were obtained by using the stacked-foil activation method and gamma-ray spectrometry. The results were compared with previous experimental data and the prediction of the TALYS nuclear reaction model code adopted from TENDL-2017 library. Physical thick target yield of 89Zr was derived from the measured cross sections.

Measurements of production cross-sections of medical radioisotopes (57Ni, 55,57,58Co, 54Mn, 51Cr) and other by-products (56Ni, 56Co, 56Mn) from the 59Co(p,x) reactions

We studied the excitation functions of 59Co(p,x) reactions and measured the production cross-sections of medical radioisotopes (57Ni, 55,57,58Co, 54Mn, 51Cr) and other by-products (56Ni, 56Co, 56Mn) from their threshold to a proton energy of 43.7 MeV. The stacked-foil activation method was employed to irradiate the samples with an external beam from the MC-50 cyclotron at the Korea Institute of Radiological and Medical Sciences (KIRAMS), Korea. Off-line γ-ray spectrometry was used to measure the activities of the produced radionuclides. The integral yields for the thick target of the investigated radionuclides were also calculated from the measured excitation functions. The measured results were compared with the literature data as well as with theoretical values obtained from the TENDL-2017 library based on the TALYS-1.9 code.

Analysis of empirical parametrization and microscopical studies of deuteron-induced reactions

A review of deuteron-induced reaction analyses is carried out paying due consideration to reaction cross-section parametrization as well as theoretical models associated to the deuteron interaction process. The key role of direct interactions, i.e., breakup, stripping and pick-up processes is stressed out by the comparison of data with theoretical and evaluation predictions, including the latest TENDL-2017 library.

A Statistical Analysis of Evaluated Neutron Resonances with TARES for JEFF-3.3, JENDL-4.0, ENDF/B-VIII.0 and TENDL-2019

In this paper, a statistical analysis of resonance evaluations from the most recent nuclear data libraries is performed with the code TARES. A description of the TARES framework is provided, but also for its use in the production of resonance parameters for the entire TENDL library. Various observables are calculated (e.g., thermal cross sections, capture integrals but also D0 and other average resonance quantities) for different libraries and compared to experimental values when available. Finally, for isotopes with no or little information, details are provided for the production of statistical resonances, based on a variety of compound nucleus reaction models.

Measurement of activation cross-sections of natDy(p,x) reactions up to 45 MeV

We activated natDy with a 45-MeV energetic proton beam and studied the production cross-sections of the reaction products 162m,161,159Ho, 159,157,155Dy, and 161,160,156,155Tb. The activation was carried out using an external beam from the MC-50 Cyclotron at the Korea Institute of Radiological and Medical Sciences, Korea. The stacked-foil activation method and off-line γ-ray spectrometry were used to measure the excitation functions of the natDy(p,x) reactions. The thick target yields of the reaction products were also estimated. The excitation functions of the natDy(p,x) reactions were theoretically calculated using TALYS 1.9 code. The measured results were compared with the literature data and the calculated values from the TENDL-2017 library and were found to be in close agreement for most of the reactions.

Excitation functions of the 165Ho(3He,xn)166,165,163Tm and natTi(3He,x)48V,48Cr reactions

The cross-sections of the natTi(3He,x)48V,48Cr and the 165Ho(3He,xn)166,165,163Tm reactions were measured from the threshold to 47 MeV using well-established method of stacked-foil activation and off-line γ-ray spectrometry. The 3He-ion induced nuclear reaction cross-sections on 165Ho were measured for the first time. Their comparison with the prediction adopted from the TENDL-2017 library revealed significant difference. Thick target yields deduced from the experimental data are provided.

Isomeric yield ratio of 196m, gAu in the 197Au(n, 2n) reaction with fast neutron based on the 9Be(p, n) reaction

The isomeric yield ratios (IR) of 196m, gAu in the 197Au(n, 2n) reaction at the average neutron energies ($ \langle E_{n}\rangle$) of 14.4, 21.8 and 29.5 MeV have been measured by using the off-line gamma-ray spectrometric technique. The neutron beams were obtained by using the 9Be(p, n) reaction with the proton energies of 25, 35 and 45 MeV from the MC-50 cyclotron at KIRAMS. The IR values at different neutron energies were also calculated from the cross sections values based on TENDL-2017 library and are found to be in agreement around 10–18 MeV but not at higher energy. The IR values of 196m, gAu at the neutron energies of 21.8 and 29.5 MeV have been measured for the first time. The present data along with the literature data at other energies in the 197Au(n, 2n) reaction are compared with the similar data in the 197Au($ \gamma$, n) reaction to examine the role of entrance channel parameters and occurrence of non-compound or pre-equilibrium process at higher projectile energy.

Measurement of deuteron-induced nuclear reactions cross-sections on 197Au and on natCu focused on the theranostic 197m,gHg

Theranostic 197m,gHg of high specific activity may be produced by proton or deuteron activation of gold. The particle choice affects the isomeric ratio. In order to compare both projectiles, we re-measured cross-sections of the nuclear reactions 197Au(d,x)197mHg, 197gHg, 198mAu, 198gAu, 196m2Au, 196m1+gAu in the energy range of 8.3–19.7 MeV having employed usual stacked-foil method. The obtained values were compared with previously measured data and with prediction of the TALYS nuclear reaction model code adopted from the TENDL-2017 library. Experimental data were used for calculation of the thick target yields. The yields for the isomeric pair 197m,gHg were confronted with those for recently re-measured proton-induced reactions. We also provide a new data set for the reaction natCu(d,x)63Zn.