Calculation Of Production Cross Sections Research Articles

Investigation of the Effects of Optical Models on the Production Cross–Section Calculations of 22,24Na Radioisotopes with some (d,x) and (α,x) Reactions

It is well recognized that the outcomes of investigations conducted in the field of basic sciences, as well as the achievements gained over the period of these studies, mediate effective and useful outcomes not only for basic sciences, but also for many other fields as diverse from engineering to medicine. In this regard, theoretical researches on the production routes of various radioisotopes that could be implemented in a numerous of fields ensure that physics and other associated areas interact on a common ground. Taking this fact into account as the motivation, the goal of this study is set to investigate how various deuteron and alpha optical models impact the cross–section calculations of 22,24Na radioisotopes, which are known to be utilized in medical applications. The TALYS (v1.95) code was utilized in the calculations, which allows for the use of five different deuteron and eight different alpha optical model alternatives. The obtained results were not only visually compared to the existing experimental data in the literature, but also quantitatively by performing mean weighted deviation and relative variance analyses.

Effects of Deuteron and Alpha Optical Model Potentials on the Production Cross–Section Calculations of Some Radiobromine Isotopes

The extensive use of radioisotopes in diverse fields, particularly in medical studies for diagnosis and treatment, is one of the outcomes of evolving technology and improved scientific research. Among the various radioisotopes used for medical purposes, an example that can be highlighted considering their properties and utilization possibilities is radiobromine isotopes. It is obvious that both experimental and theoretical studies make significant contributions to the literature on medically relevant radioisotopes. The cross–section, which is the data connected with the occurrence of a reaction, is one of the theoretical metrics that may provide information to researchers. The framework of this study was constructed by taking into account the importance of radiobromine isotopes in medical applications as well as the effects of some parameters that might have an impact on their production cross–section calculations. In this context, the impact of five deuteron and eight alpha optical model potentials, which are available in the 1.95 version of the TALYS code, on the production cross–section calculations of 75-77Br radioisotopes through some (d,x) and (α,x) reactions have been studied. The obtained calculation results were compared visually and numerically with the experimental data available in the literature for each reaction, and the outputs were interpreted.

Effects of deuteron optical model potentials on the production cross-section calculations of 66-68Ga from natZn and natGe

Since it was reported that several radioisotopes might be advantageous for different medical uses in diagnostics and therapeutics, they have gained significance. Theoretical and experimental researches on such radioisotopes have contributed to the literature on a wide variety of topics, including production route research, getting activation and yield values, optimum production method analysis, clinical effects and production cross-section calculations. This study was motivated by the studies described in this domain as well as those published in the literature. The primary purpose of this study is to investigate the effects of deuteron optical model potentials in various reactions where [Formula: see text] radioisotopes, which are known to be medically important, have been generated with deuteron induced particles on [Formula: see text] and [Formula: see text] targets. The experimental data from the literature and the calculation results generated using the five deuteron optical model potentials accessible in the TALYS code (version 1.95) were compared in line with the objective of this study. The experimental results in the literature and the data obtained as an outcome of the computations are graphically illustrated in order to comprehend these comparisons. Furthermore, to perform a numerical assessment, mean weighted deviation and relative variance calculations were also performed.

Effects of some level density models and γ-ray strength functions on production cross-section calculations of 16,18O and 24,26Mg radioisotopes

Abstract Oxygen and magnesium isotopes can be used in nuclear reactor materials as cooling, shielding, coating, electronics etc. They can also occur through nuclear reactions during the reactor operation. The exposure of high energy gamma can change the material and its properties, and hence its objective of selection may not remain satisfied. Thus, it is required to study the cross section of different reactions on nuclear reactor materials to understand their sustainability for the properties, for which they are chosen. In the scope of this study, theoretically, different level density model calculations and γ-ray strength functions have been performed for (γ, p) reaction for 16,18O and 24,26Mg nuclei using TALYS 1.9 and EMPI˙RE 3.2.2 codes. Also, semi empirical (γ, p) formula by Tel et al., have been calculated and compared with all results. The effect of different level density models defined in these codes on gamma strength has been studied. Finally, the consistency of these obtained data with EXFOR data have been investigated.

Effects of theoretical models on the production cross-section calculations of some non-standard positron emitters

Effects of theoretical models on the production cross-section calculations of some non-standard positron emitters

A Theoretical Study on the Production Cross–Section Calculations for 24Na Medical Isotope

24Na is a beta and gamma emitting radioisotope that is widely used in medical and engineering fields. It is often used in medical radiotracing. This radioisotope with a half-life of 15 hours is mostly produced in cyclotrons. The cross-section of a radioisotope is used to obtain various data about the production of that radioisotope. In cases where it is not possible to obtain experimental data, missing data can be completed with cross-section calculations and the obtained data can be compared with experimental, saving time, cost and effort. This study was carried out for detailed analysis of cross-section calculations for 24Na isotope, which has a wide range of usage in medicine and industry. In this direction, the cross-sections obtained from different simulation programs were compared with literature data of the reactions. Production cross-sections of the 24Na isotope were investigated in the 23Na(d,p)24Na, 24Mg(n,p)24Na, 25Mg(n,n+p)24Na, 25Mg(p,2p)24Na, 26Mg(d,α)24Na and 27Al(n,α)24Na reactions with the equilibrium and pre-equilibrium models of nuclear reaction codes of TALYS 1.95 and EMPIRE 3.2. Results were compared with experimental data from the EXFOR data library. The relevance of the models to the reactions was discussed and calculations were made using the relative variance analysis method to determine the best model.

Production cross-section calculations of 111In via proton and alpha-induced nuclear reactions

[Formula: see text], a known gamma emitter, is used for many medical purposes such as imaging of myocardial metastases. It can be produced by using different nuclear reactions. In this study, the reactions of [Formula: see text]Ag([Formula: see text]2n)[Formula: see text], [Formula: see text](p,[Formula: see text]n)[Formula: see text], [Formula: see text](p,[Formula: see text]2n)[Formula: see text], [Formula: see text](p,[Formula: see text]3n)[Formula: see text] and [Formula: see text](p,[Formula: see text]4n)[Formula: see text], which are the production routes of [Formula: see text], were investigated. Production cross-section calculations were performed by using equilibrium and pre-equilibrium models of TALYS 1.95 and EMPIRE 3.2 nuclear reaction codes. Hauser–Feshbach Model was appointed in both codes for calculations of equilibrium approximations. Exciton and Hybrid Monte Carlo Simulation (HMS) models were used in the EMPIRE 3.2, whereas Two-Component Exciton and Geometry Dependent Hybrid Model, which is implemented to TALYS code, has been used in the TALYS 1.95 for pre-equilibrium reactions. Also, a weighting matrix of the nuclear models was obtained by using statistical variance analysis. The optimum beam energy to obtain [Formula: see text] has been determined by using the results obtained from this weighting matrix.

A STUDY ON THE CALCULATIONS OF CROSS–SECTIONS FOR 66,67Ga AND 75Se RADIONUCLIDES PRODUCTION REACTIONS VIA 3He PARTICLES

The intend of this paper is to study on different production routes of medical 66,67Ga and 75Se radionuclides used in cancer diagnostic. Both 66,67Ga and 75Se are the most well-known radionuclides used in diagnostics of malignant and benign tumors also brain studies and scintigraphy scanning. For this purpose, production cross–section calculations of medical 66,67Ga and 75Se radionuclides have been calculated for 64Zn(3He,p)66Ga, 65Cu(3He,2n)66Ga, 65Cu(3He,n)67Ga, 66Zn(3He,n+p)67Ga, 69Ga(3He,n+a)67Ga, 76Se(3He,a)75Se, 77Se(3He,n+a)75Se reactions. In the calculations, TALYS 1.8 and ALICE/ASH computer codes have been used. The models which have been employed within the calculations are Two Component Exciton and Equilibrium of TALYS 1.8 and Hybrid and Geometry Dependent Hybrid of ALICE/ASH. The results obtained from the calculations for each reaction have been compared with other calculation results and previously recorded experimental values collected from the Experimental Nuclear Reaction Data (EXFOR) library.

Investigation of the Effects of Some Level Density Models in the Production Cross-Section Calculations of 75-77Br Radioisotopes

Radyoizotopların kullanım alanları, gelişen teknoloji ve bilimsel ilerlemeler sayesinde giderek yaygınlaşmış ve çeşitlenmiştir. Radyoizotopların en yaygın kullanıldığı alan ise medikal teşhis ve tedavi uygulamalarıdır. Bu amaçlarla kullanılan pek çok radyoizotop arasında karakteristik özellikleri ve uygulamalardaki faydaları nedeniyle 75-77Br radyoizotopları da bulunmaktadır. Medikal uygulamalarda radyoizotopların sahip oldukları etki ve değer neticesinde bu izotopların üretim rotaları ile ilgili çalışmalar da literatüre katkı sağlayan çalışmalar olmuştur. Bu kapsamda, deneysel çalışmaların gerçekleştirilemediği durumlarda araştırmacılara bilgi verebilecek çeşitli parametrelerin elde edilmesinde farklı teorik modellerin kullanımı oldukça yaygındır. Kısaca bir reaksiyonun gerçekleşme ihtimali olarak açıklanabilecek tesir kesiti değeri de araştırmacılar için önemli bir parametredir ve bu değerin hesaplanmasında etkili faktörlerden biri de seviye yoğunluğu modelleridir. Tüm bunlar göz önüne alınarak bu çalışmada, 75-77Br radyoizotoplarının bazı (p,xn) reaksiyonları ile üretim tesir kesiti hesaplamalarında bazı seviye yoğunluğu modellerinin etkilerinin araştırılması amaçlanmıştır. Hesaplamalarda TALYS kodunun 1.9 sürümü kullanılmış ve elde edilen hesaplama sonuçları literatürde mevcut olan deneysel veriler ile karşılaştırılmıştır.

Level density model effects on the production cross-section calculations of some medical isotopes via (α, xn) reactions wherex= 1–3

Level density models have an undeniable importance for a better perception on the nature of nuclear reactions, which influences our life via various ways. Many novel and advanced medical application use radioisotopes, which are produced with nuclear reactions. By considering the connection between the level density models and the importance of theoretical calculations for the production routes of medically important isotopes, this study is performed to investigate the level density model effects on the production cross-section calculations of [Formula: see text]Zn, [Formula: see text]Ga, [Formula: see text]Kr, [Formula: see text]Pd, [Formula: see text]In, [Formula: see text]I and [Formula: see text]At radioisotopes via some alpha particle induced and neutron emitting reactions. For theoretical calculations; frequently used computation tools, such as TALYS and EMPIRE codes, are applied. Obtained theoretical results are then compared with the experimental data, taken from Experimental Nuclear Reaction Data (EXFOR) library. For a better interpretation of the results, a mean weighted deviation calculation for each investigated reaction is performed in addition to a visual comparison of the graphical representations of the outcomes.

Production Cross–Section Calculations of 62Cu via Charged Particles Induced Reactions

The utilization of radioisotopes has been increasing proportionally with the scientific and industrial developments. Among many known and used examples of them, 62Cu has a wide usage due to its suitability for many specific requirements such as in medical applications. By considering the importance of radioisotopes and especially 62Cu, in this study, the theoretical calculations of cross–section values for 62Cu via 59Co(α,n)62Cu, 61Ni(d,n)62Cu, 62Ni(d,2n)62Cu and 62Ni(p,n)62Cu reactions were carried out by employing three phenomenological level density models via TALYS 1.9 code. Obtained results were compared with the available experimental data from Experimental Nuclear Reaction Data (EXFOR) Library by graphically and mathematically.

An investigation of effects of level density models and gamma ray strength functions on cross-section calculations for the production of 90Y, 153Sm, 169Er, 177Lu and 186Re therapeutic radioisotopes via (n,γ) reactions

Abstract One of the methods used to treat different cancer diseases is the employment of therapeutic radioisotopes. Therefore, many clinical, theoretical and experimental studies are being carried out on those radioisotopes. In this study, the effects of level density models and gamma ray strength functions on the theoretical production cross-section calculations for the therapeutic radioisotopes 90Y, 153Sm, 169Er, 177Lu and 186Re in the (n,γ) route have been investigated. TALYS 1.9 code has been used by employing different level density models and gamma ray strength functions. The theoretically obtained data were compared with the experimental data taken from the literature. The results are presented graphically for better interpretation.

Near-Barrier Proton Transfer in Reactions with 3He Nucleus

Calculations of production cross sections for isotopes 194Au in the 3He + 194Pt reaction and 45Ti in the 3He + 45Sc reaction are performed, based on the solution to a time-dependent Schrodinger equation in combination with calculations in the statistical model using the computational code of the NRV data base. The experimental differences in the near-barrier energy dependences of the isotope production cross sections in these reactions are explained by the difference between the proton and neutron shells of the target nuclei, and by the different evolutions of the probability density for protons of the projectile nucleus and neutrons of the target nuclei in collisions.

Production Cross–Section Calculations of Medical 177Lu Using Neutron and Proton Induced Reactions

Abstract. In this study, we aimed to investigate the alternative ways to produce 177 Lu, an isotope which has a growing rate of usage in radionuclide therapy applications. For this purpose; we analyzed the 176 Lu (n,γ) 177 Lu, 176 Yb (n,γ) 177 Yb 177 Lu, 181 Ta (n,n+α) 177-M Lu, nat W(p,x) 177 Lu reactions with the TALYS 1.6 and EMPIRE 3.2 theoretical nuclear reaction codes. Obtained results with the TALYS 1.6 and EMPIRE 3.2 codes are also compared with the experimental data exists in the literature for each reaction. Keywords: 177 Lu, Cross–Section, TALYS 1.6, EMPIRE 3.2. Ozet. Bu calismada, radyonuklit terapi uygulamalarinda giderek artan bir kullanim oranina sahip olan 177 Lu izotopu icin alternatif uretim yollarinin arastirilmasi amaclanmistir. Bu amacla; 176 Lu(n,γ) 177 Lu, 176 Yb(n,γ) 177 Yb 177 Lu, 181 Ta(n,n+α) 177-M Lu, nat W(p,x) 177 Lu reaksiyonlari TALYS 1.6 ve EMPIRE 3.2 teorik nukleer reaksiyon kodlari kullanilarak analiz edilmistir. Ayrica, TALYS 1.6 ve EMPIRE 3.2 kodlari ile elde edilen bulgular her bir reaksiyon icin literaturde mevcut deneysel veriler ile karsilastirilmistir. Anahtar Kelimeler: 177 Lu, Tesir Kesiti, TALYS 1.6, EMPIRE 3.2.

Cross section calculations of medical103Pd radioisotope using α and3He induced reactions

One of the most popular radioisotopes used in the prostate brachytherapy is Palladium-103 (103 Pd). The radioactive plaque is sewn onto the eye as to cover the intraocular tumor shadow with a 2-3 mm margin. These plaques are temporary and radiation is continuously delivered over 5 to 7 days. At the end of treatment, the plaque is removed from eye. In this study, production cross–section calculations of 103 Pd radionuclide used in brachytherapy produced by 101 Ru(α,2n), 100 Ru(α,n), 102 Ru(3 He,2n) and 101 Ru(3 He,n) reactions have been investigated in the different incident energy range up to 35 MeV. Twocomponent Exciton model and Generalized Superfluid model of the TALYS 1.6 code used to perform calculations and calculation results were compared with experimental results reported in the literature.

Influence of nuclear basic data on the calculation of production cross sections of superheavy nuclei

The center of the predicted island of stability of superheavy nuclei (SHN) has not yet been observed experimentally. Many theories are being developed to understand the synthesizing mechanism of superheavy nuclei. However, all of them have to use some basic nuclear data. Three data tables, FRDM1995 [P. M\oller et al., At. Data Nucl. Data Tables 59, 185 (1995)], KTUY2005 [H. Koura et al., Prog. Theor. Phys. 113, 305 (2005)], and WS2010 [Ning Wang et al., Phys. Rev. C 82, 044304 (2010)], are used to investigate the SHN production. Based on the dinuclear system concept, the evaporation residue cross sections of SHN for $Z$=112--118 are calculated for the $^{48}\mathrm{Ca}$-induced hot fusion reactions. It turns out that unlike the predictions made with the KTUY2005 and WS2010 data, the magic numbers $Z$=114 and $N$=184 predicted with the FRDM1995 data do not contradict the experimental data obtained so far.

Production cross–section calculations of medical 32P, 117Sn, 153Sm and 186,188Re radionuclides used in bone pain palliation treatment

Abstract In this study, production cross–section calculations of 32P, 117Sn, 153Sm and 186,188Re radionuclides used in bone pain palliation treatment produced by 30Si(d,γ)32P, 118Sn(γ,n)117Sn, 116Sn(n,γ)117Sn, 150Nd(α,n)153Sm, 154Sm(n,2n)153Sm, 152Sm(n,γ)153Sm, 186W(d,2n)186Re, 187Re(γ,n)186Re, 185Re(n,γ)186Re and 187Re(n,γ)188Re reactions have been investigated in the different incident energy range of 0.003–34 MeV. Two-component exciton and generalised superfluid models of the TALYS 1.6 and exciton and generalised superfluid models of the EMPIRE 3.1 computer codes have been used to pre-equilibrium (PEQ) reaction calculations. The calculated production cross–section results have been compared with available experimental results existing in the experimental nuclear reaction database (EXFOR). Except the 118Sn(γ,n)117Sn, 150Nd(α,n)153Sm and 185Re(n,γ)186Re reactions, the two-component exciton model calculations of TALYS 1.6 code exhibit generally good agreement with the experimental measurements for all reactions used in this present study.

Corrected ISICSoo class version

The Coster–Kronig enhancement factor calculation for M3 shell x-ray production cross sections was found to be incorrect in both ISICSoo class (Batič et al. (2012) [1]) and isics program (Cipolla (2013) [2]). The affected functions of ISICSoo class have been corrected. The resulting X-ray production cross sections are modified by less than 15%, while ionization cross sections are unchanged. NEW VERSION PROGRAM SUMMARYProgram Title: ISICSooJournal Reference:Catalogue identifier: AEKN_v1_1Program summary URL:http://cpc.cs.qub.ac.uk/summaries/AEKN_v1_1.htmlProgram obtainable from: CPC Program Library, Queen’s University, Belfast, N. IrelandLicensing provisions: Standard CPC licence, http://cpc.cs.qub.ac.uk/licence/licence.htmlNo. of lines in distributed program, including test data, etc: 26417No. of bytes in distributed program, including test data, etc: 440762Distribution format: tar.gzProgramming language: C++Computer: 80486 or higher-level PC or MacOperating system: any OS with gcc compiler version 4.1 (or newer)Classification: 16.7Catalogue identifier of previous version: AEKN_v1_0Journal reference of previous version: Comput. Phys. Comm. 183 (2012) 398–404Does the new version supersede the previous version?: yesNature of problem: Ionization and X-ray production cross section calculations for ion–atom collisions.Solution method: Numerical integration of form factor using a logarithmic transform and Gaussian quadrature, plus exact integration limits.Reasons for the new version: The Coster–Kronig enhancement factor calculation for M3 shell x-ray production cross sections was found to be incorrect in ISICSoo. The affected function has been corrected.Summary of revisions: The corresponding function members of ISICSoo class have been corrected. Fig. 1 shows the relative differences between plain PWBA x-ray production cross sections between old and new ISICSoo versions. The relative differences are largest at small energies and heavy targets, but in our calculations never surpassing 15%. Ionization cross sections were not affected by implemented correction.Running time: Same as in previous version. [Display omitted] References[1] M. Batič, M. G. Pia, S. J. Cipolla, Comp. Phys. Comm. 183 (2012), pp. 398–404.[2] S. J. Cipolla, Comp. Phys. Comm., 2013 (http://dx.doi.org/10.1016/j.cpc.2013.02.017).

ISICSoo: A class for the calculation of ionization cross sections from ECPSSR and PWBA theory

ISICS, originally a C language program for calculating K-, L- and M-shell ionization and X-ray production cross sections from ECPSSR and PWBA theory, has been reengineered into a C++ language class, named ISICSoo. The new software design enables the use of ISICS functionality in other software systems. The code, originally developed for Microsoft Windows operating systems, has been ported to Linux and Mac OS platforms to facilitate its use in a wider scientific environment. The reengineered software also includes some fixes to the original implementation, which ensure more robust computational results and a review of some physics parameters used in the computation. The paper describes the software design and the modifications to the implementation with respect to the previous version; it also documents the test process and provides some indications about the software performance. Program summary Program title: ISICSoo Catalogue identifier: AEKN_v1_0 Program summary URL: http://cpc.cs.qub.ac.uk/summaries/AEKN_v1_0.html Program obtainable from: CPC Program Library, Queenʼs University, Belfast, N. Ireland Licensing provisions: Standard CPC licence, http://cpc.cs.qub.ac.uk/licence/licence.html No. of lines in distributed program, including test data, etc.: 26 420 No. of bytes in distributed program, including test data, etc.: 459 548 Distribution format: tar.gz Programming language: C++ Computer: 80486 or higher-level PC or Mac Operating system: Any OS with gcc compiler version 4.1 (or newer); tested on Scientific Linux 5 (gcc 4.1.2), Mac OS X 10.6.5 (gcc 4.2.1) and Windows XP (MS Visual C++ 2010 Express) Classification: 16.7 Nature of problem: Ionization and X-ray production cross section calculations for ion–atom collisions. Solution method: Numerical integration of form factor using a logarithmic transform and Gaussian quadrature, plus exact integration limits. Additional comments: This program is a portable version of the program ADDS_v4_0. Reasons for the new version: Capability of using ISICS physics functionality in other software systems; porting the software to other platforms than Microsoft Windows; improved computational robustness and performance. Summary of revisions: Reengineering into a C++ class; several internal modifications to improve correctness and robustness; updated binding energies tabulations; performance improvements. Running time: The running time depends on the selected atomic shell and the number of polynomials used in the Gaussian quadrature integration. The examples provided only take seconds to run.

ISICS2011, an updated version of ISICS: A program for calculation K-, L-, and M-shell cross sections from PWBA and ECPSSR theories using a personal computer

In this new version of ISICS, called ISICS2011, a few omissions and incorrect entries in the built-in file of electron binding energies have been corrected; operational situations leading to un-physical behavior have been identified and flagged. New version program summary Program title: ISICS2011 Catalogue identifier: ADDS_v5_0 Program summary URL: http://cpc.cs.qub.ac.uk/summaries/ADDS_v5_0.html Program obtainable from: CPC Program Library, Queenʼs University, Belfast, N. Ireland Licensing provisions: Standard CPC licence, http://cpc.cs.qub.ac.uk/licence/licence.html No. of lines in distributed program, including test data, etc.: 6011 No. of bytes in distributed program, including test data, etc.: 130 587 Distribution format: tar.gz Programming language: C Computer: 80486 or higher-level PCs Operating system: WINDOWS XP and all earlier operating systems Classification: 16.7 Catalogue identifier of previous version: ADDS_v4_0 Journal reference of previous version: Comput. Phys. Commun. 180 (2009) 1716. Does the new version supersede the previous version?: Yes Nature of problem: Ionization and X-ray production cross section calculations for ion–atom collisions. Solution method: Numerical integration of form factor using a logarithmic transform and Gaussian quadrature, plus exact integration limits. Reasons for new version: General need for higher precision in output format for projectile energies; some built-in binding energies needed correcting; some anomalous results occur due to faulty read-in data or calculated parameters becoming un-physical; erroneous calculations could result for the L and M shells when restricted K-shell options are inadvertently chosen; to achieve general compatibility with ISICSoo, a companion C++ version that is portable to Linux and MacOS platforms, has been submitted for publication in the CPC Program Library approximately at the same time as this present new standalone version of ISICS [1]. Summary of revisions: The format field for projectile energies in the output has been expanded from two to four decimal places in order to distinguish between closely spaced energy values. There were a few entries in the executable binding energy file that needed correcting; K shell of Eu, M shells of Zn, M1 shell of Kr. The corrected values were also entered in the ENERGY.DAT file. In addition, an alternate data file of binding energies is included, called ENERGY_GW.DAT, which is more up-to-date [2]. Likewise, an alternate atomic parameters data file is now included, called FLOURE_JC.DAT, which is more up-to-date [3] fluorescence yields for the K and L shells and Coster–Kronig parameters for the L shell. Both data files can be read in using the -f usage option. To do this, the original energy file should be renamed and saved (e.g., ENERGY_BB.DAT) and the new file (ENERGY_GW.DAT ) should be duplicated as ENERGY.DAT to be read in using the -f option. Similarly for reading in an alternate FLOURE.DAT file. As with previous versions, the user can also simply input different values of any input quantity by invoking the “specify your own parameters” option from the main menu. You can also use this option to simply check the values of the built-in values of the parameters. If it still happens that a zero binding energy for a particular sub-shell is read in, the program will not completely abort, but will calculate results for the other sub-shells while setting the affected sub-shell output to zero. In calculating the Coulomb deflection factor, if the quantity inside the radical sign of the parameter z s z s = ( 1 − ( 4 / M ζ s θ s ) ( ζ s / ξ s ) ) 2 becomes zero or negative, to prevent the program from aborting, the PWBA cross sections are still calculated while the ECPSSR cross sections are set to zero. This situation can happen for very low energy collisions, such as were noticed for helium ions on copper at energies of E ⩽ 11.2 keV . It was observed during the engineering of ISICSoo [1] that erroneous calculations could result for the L- and M-shell cases when restricted K-shell R or HSR scaling options were inappropriately chosen. The program has now been fixed so that these inappropriate options are ignored for the L and M shells. In the previous versions, the usage for inputting a batch data file was incorrectly stated in the Users Manual as -Bxxx; the correct designation is -Fxxx, or alternatively, -Ixxx, as indicated on the usage screen in running the program. A revised Users Manual is also available. Restrictions: The consumed CPU time increases with the atomic shell (K, L, M), but execution is still very fast. Running time: This depends on which shell and the number of different energies to be used in the calculation. The running time is not significantly changed from the previous version.