Nuclear Reaction Cross Section Data Research Articles

New Method for 18FDG generating using Geant4/ Gate7

Fluorine 18-deoxyglucose is often used in Positron Emission Tomography devices. Positron Emission Tomography imaging is one of the useful tool which is used for cancer detection and its management. Positron Emission Tomography growth is limited due to problems that depend on the production of Fluorine-18. Imaging results are strongly depending on the information of nuclear reaction cross section data. This study is presented to calculate different quantities such as stopping power, CSDA range, simulated and distributed absorbed dose of Fluorine-18 in water. In order to access these goals, we use Geant4/Gate7 simulation and the Bethe-Bloch model. The results of this simulation and theoretical model presented are in good agreement with each other. The important point of this paper is the presentation of a theoretical approach in order to the production of Fluorine-18 using protons generated through the main D(d;p)Tand side 3 He(d;p)4 He nuclear fusion reaction in which uses Helium-3 is catalyzed.

An overview of nuclear data standardisation work for accelerator-based production of medical radionuclides in Pakistan

Abstract The standardisation of nuclear reaction cross section data is an integral part of optimisation of production routes of medical radionuclides. The production cross sections are available for the reactor and cyclotron produced radionuclides to be used for diagnostics or therapeutic procedures. The types of nuclear data needed, and the sources of their availability are summarized. The method of standardisation of charged-particle data is briefly described. A historical overview of research work in Pakistan in this direction is given. Examples of a few medically important radionuclides, such as 64Cu, 86Y, 89Zr, 103Pd, 186Re, etc., whose data were standardised and evaluated are highlighted. Calculated thick target yields from the recommended data are given. Some new directions in the nuclear data research are outlined.

Systematical analysis of (n,2n) reaction cross sections for 14-15 MeV neutrons

Fast neutron induced nuclear reaction cross section data are necessary for both nuclear energy technology and the understanding of fundamental nuclear physics problems. The information of (n,2n) cross sections is quite essential in nuclear technology as a significant portion of the fission neutron spectrum lies above the threshold of (n,2n) reaction for mostof the reactor materials. These cross section data are required in shielding and breeding calculations. Radioactive nuclides produced in the reactor usually have short half-life. So, direct measurement of their neutron cross sections is difficult. Therefore, model formulae are important to predict these cross sections theoretically. In this work, in the framework of the statistical model we deduced some theoretical formulae for the (n,2n) cross section using the evaporation model, constant nuclear temperatureapproximation and Weizsäker’s formula for binding energy. The model formulae were utilized for systematical analysis of known experimental data of the (n,2n) cross sections at 14 - 15 MeV energy.

Continuing Nuclear Data Research for Production of Accelerator-Based Novel Radionuclides for Medical Use: A Mini-Review

Nuclear data are important for production and medical application of a radionuclide. This brief review concentrates on nuclear reaction cross-section data. The availability of standardized nuclear data for accelerator-based production of medical radionuclides is outlined. Some new directions in radionuclide applications, for example, theranostic approach, bimodal imaging, and radionuclide targeted therapy, are considered and the status of relevant nuclear data is discussed. The current trends in nuclear data research using accelerators are elaborated. The increasing significance of intermediate energy accelerators in production of therapeutic radionuclides is emphasized.

Investigation of neutron-induced reaction cross section calculations for the fusion reactor structural materials using artificial neural networks

Using artificial neural networks for an estimation of the nuclear reaction cross section data is discussed. Approximately rate of the fitting criteria is determined by the calculated experimental data obtained from using Variable Learning Rate Backpropagation (traingdx) algorithm in artificial neural networks. This method has been applied to obtain the cross section for 14–15 MeV neutron-induced (n,α) and (n,p) reactions in the fusion reactor structural materials. In comparison to the reaction cross section calculation by experimental cross sections reported in EXFOR, TALYS 1.9 and EMPIRE 3.2, the proposed method has better prediction ability when the target output has a large variation between the experimental and the calculated data. This study is substantial for the new method validation development of the nuclear model approaches with the increased prediction power of the neutron-induced reactions for fusion reactor systems.

A new study on (n, p) cross sections in nuclear interactions of neutrons with dysprosium

Neutron-induced nuclear reaction cross section data on dysprosium (Dy) target material are needed for the development and design of reactors, because of using Dy such as an absorbing material for the control rods in reactors. Furthermore, these data are important in terms of improving the definition of neutron–particle interaction. In this framework, the excitation functions of 156,158,160–164Dy(n, p)156,158,160–164Tb reactions were theoretically calculated using TALYS 1.8 and EMPIRE 3.2 Malta nuclear reaction codes. In addition, effects of different level density models on the reaction cross sections were also investigated. Therefore, the obtained theoretical cross sections are compared with the experimental cross sections found in the literature. Besides, (n, p) cross section systematics, which was proposed in our previous article and in the literature, has been used for obtaining the reaction cross sections at energies of around 14 MeV.

Double differential cross section calculations for 16O and 90Zr elements

Double differential cross sections in proton induced reactions on 90Zr and O2 (inert matrix fuel) is calculated at the bombarding energies between 29 and 300 MeV. The proton-induced nuclear reaction cross section data can be used in technical applications such as the isotope production alternatives, spallation reactions for production of neutrons in spallation neutron source, etc. In this study, the cascade excition model including the effect of preequilibrium is used to calculate the differential cross section. Then, the obtained results are discussed and compared with available experimental data.

Evaluation of nuclear reaction cross section data for the production of 87Y and 88Y via proton, deuteron and alpha-particle induced transmutations

Proton, deuteron and alpha-particle induced reactions on 87,88Sr, natZr and 85Rb targets were evaluated for the production of 87,88Y. The literature data were compared with nuclear model calculations using the codes ALICE-IPPE, TALYS 1.6 and EMPIRE 3.2. The evaluated cross sections were generated; therefrom thick target yields of 87,88Y were calculated. Analysis of radio-yttrium impurities and yield showed that the 87Sr(p, n)87Y and 88Sr(p, n)88Y reactions are the best routes for the production of 87Y and 88Y respectively. The calculated yield for the 87Sr(p, n)87Y reaction is 104 MBq/μAh in the energy range of 14→2.7MeV. Similarly, the calculated yield for the 88Sr(p, n)88Y reaction is 3.2 MBq/μAh in the energy range of 15→7MeV.

Deuteron Induced (d,p) and (d,2p) Nuclear Reactions up to 50 MeV

Many studies have shown that the nuclear reactions of charged particles with nuclei are very important in many fields of nuclear physics. The interactions of deuterons with nuclei have been especially the subject of common research in the history of nuclear physics. Moreover, the knowledge of cross section for deuteron-nucleus interactions are required for various application such as space applications, accelerator driven sub-critical systems, nuclear medicine, nuclear fission reactors and controlled thermonuclear fusion reactors. Particularly, the future of controlled thermonuclear fusion reactors is largely dependent on the nuclear reaction cross section data and the selection of structural fusion materials. Finally, the reaction cross section data of deuteron induced reactions on fusion structural materials are of great importance for development and design of both experimental and commercial fusion devices. In this work, reaction model calculations of the cross sections of deuteron induced reactions on structural fusion materials such as Al (Aluminium), Ti (Titanium), Cu (Copper), Ni (Nickel), Co (Cobalt), Fe (Iron), Zr (Zirconium), Hf (Hafnium) and Ta (Tantalum) have been investigated. The new calculations on the excitation functions of 27Al(d,2p)27Mg, 47Ti(d,2p)47Sc, 65Cu(d,2p)65Ni, 58Ni(d,2p)58Co, 59Co(d,2p)59Fe, 58Fe(d,p)59Fe, 96Zr(d,p)97Zr, 180Hf (d,p)181Hf and 181Ta(d,p)182Ta have been carried out for incident deuteron energies up to 50 MeV. In these calculations, the equilibrium and pre-equilibrium effects for (d,p) and (d,2p) reactions have been investigated. The equilibrium effects are calculated according to the Weisskopf-Ewing (WE) Model. The pre-equilibrium calculations involve the new evaluated the Geometry Dependent Hybrid Model (GDH) and Hybrid Model. In the calculations the program code ALICE/ASH was used. The calculated results are discussed and compared with the experimental data taken from the literature.

Radiochemical determination of nuclear data for theory and applications

A vast knowledge of nuclear data is available and is grouped under three headings, namely, nuclear structure, nuclear decay and nuclear reaction data. Still newer aspects are under continuous investigation. Data measurements are done using a large number of techniques, including the radiochemical method, which has been extensively worked out at Julich. This method entails preparation of high-quality sample for irradiation, isolation of the desired radioactive product from the strong matrix activity, and preparation of thin source suitable for accurate measurement of the radioactivity. It is especially useful for fundamental studies on light complex particle emission reactions and formation of low-lying isomeric states, both of which are rather difficult to describe by nuclear model calculations. The neutron induced reaction cross section data are of practical application in fusion reactor technology, particularly for calculations on tritium breeding, gas production in structural materials and activation of reactor components. The charged particle induced reaction cross section data, on the other hand, are of significance in medicine, especially for developing new production routes of novel positron emitters and therapeutic radionuclides at a cyclotron. Both neutron and charged particle data also find application in radiation therapy. A brief overview of advances made in all those areas is given, with major emphasis on nuclear reaction cross section data.

Nuclear data relevant to the production and application of diagnostic radionuclide

The types of nuclear data and their quality required in the production and application of diagnostic radionuclides are outlined. The radioactive decay data determine the suitability of a radioisotope forin vivotracer studies, both from the imaging and internal radiation dose considerations. The nuclear reaction cross section data allow optimisation of production routes. Both reactors and cyclotrons are used for production purposes. The nuclear data needed in the two cases and their present status are discussed. Special attention is paid to radionuclides suitable for emission tomography (PET and SPECT). The controversy aboutreactorvscyclotronproduction of the widely used99Mo/99mTc generator system is discussed. Some special considerations in cyclotron production of radionuclides are outlined. The need of accurate data near reaction thresholds, the constraint of available particles and their energies at a small cyclotron, the influence of increasing incident particle energy, and the formation of isomeric impurities are discussed in detail. The role of nuclear model calculations in predicting unknown data is considered.

Nuclear data for medical applications: an overview

A brief introduction to nuclear data in medicine is given. The choice of a radioisotope for medical application demands an accurate knowledge of radioactive decay data. Short-lived single photon and β+-emitters are preferred for diagnostic investigations, and longer-lived corpuscular radiation emitting radioisotopes for endoradiotherapy. The nuclear reaction cross section data, on the other hand, are needed for optimising the production routes. Besides radioactive isotopes, the use of ionising radiation in therapy is discussed. External radiation therapy has achieved an important place in medicine. The role of nuclear data is briefly discussed; they are needed for radiation dose calculations. The hitherto rather neglected activation products in proton therapy are considered. The methodology of development of a nuclear data file for medical applications is outlined