A function to provide neutron spectrum produced from the ⁹Be  + p reaction with protons of energy below 12 MeV

Figures & data

Figure 1. Total cross section of neutron production by p–Be. Dots are the available experimental data [18,19]. The solid line was obtained using the function.

Figure 2. Angular distribution. Dots are the available experimental data [7,20–22]. The solid line was obtained using the function.

Figure 3. Energy spectrum. Dots are the available experimental data [21]. The solid line was obtained using the function.

Figure 4. Results of the calculation using our function for the neutron energy spectra at angles of 0°, 20°, 40°, 60°, 80°, 110°, and 140° under the condition of E_p = 4 MeV with a 0.5-mm-thick Be target. Solid lines are the calculations using the FS. Dots are existing data [23].

Figure 5. Results of the calculation using our function for the neutron energy spectra at angles of 0°, 20°, 40°, 60°, 80°, 110°, and 140° under the condition of E_p = 4 MeV with a 0.5-mm-thick Be target. The thick solid lines show the calculations with the function. Dots are existing data [23]. Dashed lines were obtained using ENDF/B-VII.0. Thin solid lines were obtained using JENDL4.0/HE.

Figure 6. Results of the calculations using our function, ENDF/B-VII.0, and JENDL4.0/HE for neutron energy spectra at angles of 0°, 15°, 30°, 60°, 90°, and 120° under the condition of E_p = 12 MeV with a 2-mm-thick Be target. Solid lines show the calculations using the function. Dots are recent experimental data [8]. Dashed lines were obtained using ENDF/B-VII.0. Thin solid lines were obtained using JENDL4.0/HE.

Figure 7. Schematic cross-sectional view of RANS downstream of the proton accelerator and enlarged view around the Be target.

Table 1. Comparison of the reaction rate of In5n. The C/E ratio is the calculated result divided by the experimental value

	Reaction rate [1/s/100 μA]	C/E ratio
Experimental value	2.55 ±  20 × 10^−17	–
Calculation with the CF	2.91 × 10^−17	1.14 ±  0.07
Calculation with ENDF/B-VII.0	1.66 × 10^−17	0.65 ± 0.04

Figure 8. Neutron flux spectra at a distance of 5 m from the moderator. The thick solid line indicates the spectrum obtained using the source neutron of CF. The thin solid line shows that obtained using our original source neutron [16,17]. The dotted line indicates the cross section of the ¹¹⁵In(n,n’)^115mIn reaction.

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