The theoretical studies of charged particle induced reactions are important to improve and study the radioisotope production, especially in reactions where the experimental data are incomplete or insufficient. In this study, cross section of alpha induced of 92,94,95Mo isotopes are calculated and analyzed by using different alpha optical model potentials and nuclear level density models with TALYS code. The effects of alpha optical model potentials and nuclear level density are analyzed separately and together for each reaction. To determine the best combination of models, chi-squared values are calculated for all combination cases. The commonly used program is TALYS to calculate the reaction cross section. For the calculations, the latest version of TALYS nuclear code version 1.96 is used. The experimental data are taken carefully for all reactions from experimental nuclear reaction data base (EXFOR). The obtained results are compared with these data and discussed. A good agreement between the calculated and experimental data is clearly presented for all analyzed reactions. It is seen from the results that alpha optical model potentials and nuclear level density models have an effective role on cross section calculations of alpha induced reactions.

OBJECTIVE: The purpose of this study was to present the classification of navicular bones and the anatomical basis for the diagnosis and treatment of navicular fractures of the foot.
METHODS: 351 computed tomographic (CT) images of the navicular bone were analyzed and classified. The navicular bone\'s anatomical morphology was measured by three independent researchers in each type. Analysis and recording of the measurement results followed.
RESULTS: Navicular bones were assorted into three types: I shape(37.04%), II shape(54.41%), and III shape(8.55%). The left and right sides did not differ in any appreciable ways, except ab, bc, and ∠abc (P < 0.05); And all data were statistically different between men and women except for ∠abc (p > 0.05).
CONCLUSIONS: The classification of the navicular bone in this study may be helpful in making the treatment decision for navicular fracture.
METHODS: 4.

The article reports the production yields of the medically relevant Ru radionuclides and other co-produced radionuclides from 6,7Li-induced reactions on 93Nb target within the 20-45 MeV energy range. The residues were measured employing the activation technique followed by the offline γ-spectroscopy. Statistical model calculations using EMPIRE3.2.2 code are employed to assess the optimized nuclear model parameters and production mechanisms of the residues. As an outcome, new data from 6Li reaction suggests 9720 MBq/C of thick target yield (TTY) for the production of 95Ru with minimal impurities. While 7Li reaction may be relied upon for producing 97Ru, yielding 813 MBq/C TTY within the studied energy range.

Accurate measurements of photonuclear reaction cross sections are crucial for a number of applications, including radiation shielding design, absorbed dose calculations, reactor physics and engineering, nuclear safeguard and inspection, astrophysics, and nuclear medicine. Primarily motivated by the study of the production of selected radionuclides with high-energy photon beams (mainly 225Ac, 47Sc, and 67Cu), we have established a methodology for the measurement of photonuclear reaction cross sections with the microtron accelerator available at the Swiss Federal Institute of Metrology (METAS). The proposed methodology is based on the measurement of the produced activity with a High Purity Germanium (HPGe) spectrometer and on the knowledge of the photon fluence spectrum through Monte Carlo simulations. The data analysis is performed by applying a Bayesian fitting procedure to the experimental data and by assuming a functional trend of the cross section, in our case a Breit-Wigner function. We validated the entire methodology by measuring a well-established photonuclear cross section, namely the 197Au(γ, n)196Au reaction. The results are consistent with those reported in the literature.

Cross sections of the 54Fe(n,p)54Mn, 54Fe(n,α)51Cr, 56Fe(n,p)56Mn and 204Pb (n,2n)203Pb reactions induced by D-T neutrons were obtained with activation method and γ-ray spectrometry technique. Experimental values measured in this work are consistent with most of the previous literature data. These reactions cross sections were theoretically calculated by using the TALYS-1.96 and EMPIRE-3.2.3 codes from threshold up to 20 MeV, and significant discrepancies were found between calculated results and experiment data. In addition, experimental values are compared with evaluated nuclear data of the CENDL-3.2, ENDF/B-VIII.0, JENDL-5, BROND-3.1 and JEFF-3.3 libraries, and significant difference was found for the 54Fe(n,α)51Cr reaction in ENDF/B-VIII.0 library but not for other reactions.

This work analyzes hemodynamic phenomena within the aorta of two elderly patients and their impact on blood flow behavior, particularly affected by an endovascular prosthesis in one of them (Patient II). Computational Fluid Dynamics (CFD) was utilized for this study, involving measurements of velocity, pressure, and wall shear stress (WSS) at various time points during the third cardiac cycle, at specific positions within two cross sections of the thoracic aorta. The first cross-section (Cross-Section 1, CS1) is located before the initial fluid bifurcation, just before the right subclavian artery. The second cross-section (Cross-Section 2, CS2) is situated immediately after the left subclavian artery. The results reveal that, under regular aortic geometries, velocity and pressure magnitudes follow the principles of fluid dynamics, displaying variations. However, in Patient II, an endoprosthesis near the CS2 and the proximal border of the endoprosthesis significantly disrupts fluid behavior owing to the pulsatile flow. The cross-sectional areas of Patient I are smaller than those of Patient II, leading to higher flow magnitudes. Although in CS1 of Patient I, there is considerable variability in velocity magnitudes, they exhibit a more uniform and predictable transition. In contrast, CS2 of Patient II, where magnitude variation is also high, displays irregular fluid behavior due to the endoprosthesis presence. This cross-section coincides with the border of the fluid bifurcation. Additionally, the irregular geometry caused by endovascular aneurysm repair contributes to flow disruption as the endoprosthesis adjusts to the endothelium, reshaping itself to conform with the vessel wall. In this context, significant alterations in velocity values, pressure differentials fluctuating by up to 10%, and low wall shear stress indicate the pronounced influence of the endovascular prosthesis on blood flow behavior. These flow disturbances, when compounded by the heart rate, can potentially lead to changes in vascular anatomy and displacement, resulting in a disruption of the prosthesis-endothelium continuity and thereby causing clinical complications in the patient.

In this paper we want to study (n,3n) reactions using an empirical formula derived on the basis of the statistical model considering reaction Q-value dependence. This formula was obtained by taking into account the exponential dependence on asymmetry parameter (N-Z)/A for neutron-induced reactions in Levkovskii\'s empirical formula. In addition, the present formula depends also on incident energy En, reaction Q-value and symmetry term (N-Z)2/A. Herein, a new analysis of experimental data of (n,3n) reactions in the energy region 22-27.5 MeV was carried out for quick estimation of cross sections of the heavy mass isotopes of odd Z-even N nuclides in the region of A = 151 to 209. We observed a good agreement of the experimental cross section data with the calculations performed using the present empirical formula.

Objective. Proton therapy currently faces challenges from clinical complications on organs-at-risk due to range uncertainties. To address this issue, positron emission tomography (PET) of the proton-induced11C and15O activity has been used to provide feedback on the proton range. However, this approach is not instantaneous due to the relatively long half-lives of these nuclides. An alternative nuclide,12N (half-life 11 ms), shows promise for real-timein vivoproton range verification. Development of12N imaging requires better knowledge of its production reaction cross section.Approach. The12C(p,n)12N reaction cross section was measured by detecting positron activity of graphite targets irradiated with 66.5, 120, and 150 MeV protons. A pulsed beam delivery with 0.7-2 × 108protons per pulse was used. The positron activity was measured during the beam-off periods using a dual-head Siemens Biograph mCT PET scanner. The12N production was determined from activity time histograms.Main results. The cross section was calculated for 11 energies, ranging from 23.5 to 147 MeV, using information on the experimental setup and beam delivery. Through a comprehensive uncertainty propagation analysis, a statistical uncertainty of 2.6%-5.8% and a systematic uncertainty of 3.3%-4.6% were achieved. Additionally, a comparison between measured and simulated scanner sensitivity showed a scaling factor of 1.25 (±3%). Despite this, there was an improvement in the precision of the cross section measurement compared to values reported by the only previous study.Significance. Short-lived12N imaging is promising for real-timein vivoverification of the proton range to reduce clinical complications in proton therapy. The verification procedure requires experimental knowledge of the12N production cross section for proton energies of clinical importance, to be incorporated in a Monte Carlo framework for12N imaging prediction. This study is the first to achieve a precise measurement of the12C(p,n)12N nuclear cross section for such proton energies.

Numerous research endeavours have delved into comprehending the dynamics of the (n,3He) reaction cross sections. In this study, a novel and straightforward empirical formula is put forth, aimed at swiftly computing the cross sections of the (n,3He) reaction in the neutron energy range of 14-15 MeV. This new formula has been obtained using outcomes from pre-existing cross section formulas in conjunction with experimental data. The present formulation, hinging on the interplay of A23 parameter, threshold energy (Eth) and incident neutron energy (En) factors, appears to furnish a satisfactory methodology for elucidating the cross sections of the neutron-induced (n,3He) nuclear reaction at 14-15 MeV. Finally, in this paper, a comparison is made between the results of the empirical formula and the experiment.

Production cross sections of medical radionuclides 111In, 110mIn and 109Cd were investigated in the α-particle-induced reactions on natural silver up to 50 MeV. The stacked-foil activation technique and γ-ray spectrometry were used to determine the cross sections. The excitation functions of byproducts 104g,105,106m,110mAg, 107,111mCd and 107g,108g,108m,109,110gIn were also determined. Physical yields of 111In, 110mIn and 109Cd were deduced based on the measured cross sections.