A Monte-Carlo Simulation Method for Neutron Yield and Spectrum in (α, n) Reaction

doi:10.19596/j.cnki.1001-246x.8287

Abstract

Abstract:

A direct Monte-Carlo simulation method was developed to calculate neutron yield and spectrum in (α, n) reaction. It is based on continuous collision method, using stopping power computed by the program SRIM to simulate the moderation of α-particle and the ACE format of the nuclear data library JENDL/AN-2005 to calculate the neutron yield and spectrum in (α, n) reaction. Moreover, a (α, n)-simulator was developed based on the program NPTS. (α, n) neutron yields of light nuclides obtained in our simulations are consistent with experiments. In terms of (α, n) neutron spectrum, our results are in good agreement with experiments in the cases of B, F and O targets, while deviations are present in the cases of C, Al and Si.

Key words: (α, n) reaction, Monte-Carlo simulation, neutron yield, neutron spectrum

CLC Number:

O571.5

Bo YANG, Bin ZHONG, Qi XU, Li CHENG, Liujun PAN, Huayun SHEN. A Monte-Carlo Simulation Method for Neutron Yield and Spectrum in (α, n) Reaction[J]. Chinese Journal of Computational Physics, 2021, 38(4): 393-400.

Figures/Tables 17

References 13

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Nuclide	Threshold/MeV	Nuclide	Threshold/MeV	Nuclide	Threshold/MeV
⁶Li	6.62	¹³C	0.0	²³Na	3.48
⁷Li	4.38	¹⁴N	6.09	²⁷Al	3.03
⁹Be	0.0	¹⁵N	8.13	²⁸Si	9.25
¹⁰B	0.0	¹⁷O	0.0	²⁹Si	1.74
¹¹B	0.0	¹⁸O	0.85	³⁰Si	3.96
¹²C	11.34	¹⁹F	2.36

Nuclide	Threshold/MeV	Nuclide	Threshold/MeV	Nuclide	Threshold/MeV
⁶Li	6.62	¹³C	0.0	²³Na	3.48
⁷Li	4.38	¹⁴N	6.09	²⁷Al	3.03
⁹Be	0.0	¹⁵N	8.13	²⁸Si	9.25
¹⁰B	0.0	¹⁷O	0.0	²⁹Si	1.74
¹¹B	0.0	¹⁸O	0.85	³⁰Si	3.96
¹²C	11.34	¹⁹F	2.36

Incident energy/MeV	Neutron yield/10^-6
Incident energy/MeV	Jacobs, 1983	West, 1982	Bair, 1979	Simulation
4.0	5.6±0.3	6.24±0.25		5.95
4.5	10.5±0.6	10.6±0.4		10.40
5.0	15.6±0.9	15.6±0.6		15.54
5.5	20.6±1.2	20.6±0.8		20.61

Incident energy/MeV	Neutron yield/10^-6
Incident energy/MeV	Jacobs, 1983	West, 1982	Bair, 1979	Simulation
4.0	5.6±0.3	6.24±0.25		5.95
4.5	10.5±0.6	10.6±0.4		10.40
5.0	15.6±0.9	15.6±0.6		15.54
5.5	20.6±1.2	20.6±0.8		20.61

Incident energy/MeV	Neutron yield/10^-8
Incident energy/MeV	Jacobs, 1983	West, 1982	Bair, 1979	Simulation
4.0	3.9±0.4	4.2±0.3	4.33±0.06	4.04
4.5	4.6±0.5	4.8±0.4	4.97±0.07	4.66
5.0	6.1±0.4	6.3±0.3	6.47±0.1	6.24
5.5	10.1±0.9	10.8±0.5	11.2±0.2	11.07