Determination of neutron spectrum parameters at IREN facility using the MCNP simulation and experimental validation
The determination of the characteristics of neutron spectrum at different irradiation positions on the outer wall of moderator chamber of the intense resonance neutron source by simulation method using MCNP code was presented. The characteristics of neutron spectrum including the flux of th...
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| Main Authors: | , , , , , , , , , , , , , , |
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| Format: | Article |
| Language: | English |
| Published: |
VINCA Institute of Nuclear Sciences
2025-01-01
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| Series: | Nuclear Technology and Radiation Protection |
| Subjects: | |
| Online Access: | https://doiserbia.nb.rs/img/doi/1451-3994/2025/1451-39942501010N.pdf |
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| Summary: | The determination of the characteristics of neutron spectrum at different
irradiation positions on the outer wall of moderator chamber of the intense
resonance neutron source by simulation method using MCNP code was presented.
The characteristics of neutron spectrum including the flux of thermal,
epithermal and fast neutron, neutron temperature and a-shape parameter have
been determined. For validation of MCNP simulation, the characteristics of
neutron spectrum at the optimal irradiation position were determined
experimentally by activation technique. The comparison shows that the
simulated and experimental results are in agreement, which indicates the
high reliability of MCNP code except for a-shape parameter. Our revised
equation for determination of a shape parameter by the method of
cadmium-ratio for multi-monitor has been used, in which the correction
coefficients of the epithermal neutron transmission for cadmium cover, the
thermal and epithermal neutron self-shielding, were included for improvement
of the accuracy. The calculated and measured a-shape parameters are in
good agreement when our proposed revised equation is used. |
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| ISSN: | 1451-3994 1452-8185 |