## 3 Results  
Table 2 presents a comparison between the interaction potential parameters calculated at various neutron energies using SHF-WS densities and the theoretical values reported by [PERSON] and [PERSON] [43]. A neutron incident energy of 14 MeV was selected as a reference point for cross-section calculations across all \({}^{182,183,184,186}\)W isotopes. Additional neutron energies were selected in accordance with the available experimental cross-section data for these isotopes. The spherical neutron parameters' energy and mass number for nuclei in the range \(0.001\leq\mathrm{E}\leq 200\) MeV and \(24\leq\mathrm{A}\leq 209\) are given by [43]:  
\[r_{v}=1.3039-0.4054A^{-1/3}, \tag{15}\]  
\[a_{v}=0.6778-1.487\times 10^{-4}\mathrm{A}. \tag{16}\]  
In the OM, the real volume potential is typically described using a WS form, which includes two important geometrical parameters:  
\(r_{v}\): This is the geometric radius parameter of the real central (volume) potential. \(a_{v}\): This is the diffuseness parameter, controlling the surface smoothness of the real central potential. It defines how smoothly the potential falls off at the nuclear surface. A typical value is around 0.65 fm, though it may vary slightly depending on the specific global or local fit. These parameters are crucial in determining the shape and strength of the nuclear potential felt by the incoming nucleon (neutron or proton). They are adjusted as part of the fitting process to match experimental scattering and reaction data. The angular differential cross-section curves, computed using TALYS 1.96 with the \(r_{v}\) and \(a_{v}\) parameters from Table 2 and the interaction potentials \(V_{0}\) listed in Table 3, are compared with both theoretical predictions and experimental data. The values calculated with the NRV-based FRESCO code, using theoretical parameters from the literature [32; 33], alongside the experimental results obtained from the EXFOR database, are presented in Figures 4-7 for each tungsten isotope. Neutron incident energies used in the analysis of \({}^{182,183,184,186}\)W isotopes were selected based on the corresponding experimental data available in the EXFOR database [12]. In addition, 14 MeV commonly used in neutron scattering experiments was included as a standard benchmark energy. The projectile energies used as input parameters for neutrons are also provided in Table 3. \begin{table}
\begin{tabular}{c c c} \hline \(\mathbf{W}\) & \(\mathbf{r}_{0}\)(\(\mathbf{f}\mathbf{m}\)) & \(\mathbf{a}_{v}\)(\(\mathbf{f}\mathbf{m}\)) \\ \hline \({}^{182}\)W & 1.2324 & 0.6507 \\ \({}^{183}\)W & 1.2325 & 0.6506 \\ \({}^{184}\)W & 1.2326 & 0.6504 \\ \({}^{186}\)W & 1.2329 & 0.6501 \\ \hline \end{tabular}
\end{table} 
Table 2: Calculated theoretical \(r_{v}\) and \(a_{v}\) parameters. \begin{table}
\begin{tabular}{c c c c c} \hline \multirow{2}{*}{**Reaction**} & **Energy** & **Experimental** & **Koning and Delaroche** & **SHF-WS** \\  & **(MeV)** & \(\mathbf{V_{0}}\) **(MeV)** & \(\mathbf{V_{0}}\) **(MeV)** & \(\mathbf{V_{0}}\) **(MeV)** \\ \hline \multirow{6}{*}{\({}^{182}\)W} & 1.5 & 49.5 [68] & \(-\)48.234 & \(-\)47.7239 \\  & 2.5 & 49.0 [68] & \(-\)47.893 & \(-\)47.5772 \\  & 3. Figure 4: Angular differential cross sections for \({}^{182}\)W(n,el) at **(a)** 1.5 MeV [43; 68], **(b)** 2.5 MeV [43; 68], **(c)** 3.4 MeV [6; 43], **(d)** 4.87 MeV [43; 69], **(e)** 6 MeV [43; 69], and **(f)** 14 MeV [43] neutron incident energies. \begin{table}
\begin{tabular}{c c c c c} \hline \multirow{2}{*}{**Reaction**} & **Energy** & **Experimental** & **Koning and Delaroche** & **SHF-WS** \\  & **(MeV)** & \(V_{\theta}\) **(MeV)** & \(V_{\theta}\) **(MeV)** & \(V_{\theta}\) **(MeV)** \\ \hline \multirow{4}{*}{\({}^{186}\)W} & 1.5 & 49.5 [68] & \(-\)47.834 & \(-\)47.1878 \\  & 2.5 & 49.0 [68] & \(-\)47.496 & \(-\)47.0439 \\ \cline{1-1}  & 3.4 & 50.1 [6] & \(-\)47.194 & \(-\)46.9144 \\ \cline{1-1}  & 14 & NA & \(-\)43.727 & \(-\)45.391 \\ \hline \end{tabular}
\end{table}