A Study of Nuclear Fuel Burnup Wave Development in a Fast Neutron Energy Spectrum Multiplying Medium: Improved Model and Consistent Parametric Approach for Evaluation

<span>The research about the characterization of neutron energy spectrum as the effect of thickness variation of beryllium (Be) target on HM−30 cyclotron using Monte Carlo N−Particle eXtended (MCNP−X) has been conducted. This research aims to know the characteristics of neutron energy spectrum which are the result ofed by the reaction of Be(p,n) with HM−30 cyclotron as one of BNCT facilities. Modelling and simulation have been done by using MNCP−X software, then the data obtained is arranged on a graph by using Origin 8+. The result of the simulation shows that the characteristics of neutron energy spectrum of each thickness are in the range of fast neutron energy. The thicker the Beryllium target, the more diminishing the neutron energy will be.</span>

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Finite temperature effect on knock-on ion production and neutron energy spectrum in deuteron–triton fusion plasma

Journal of Plasma Physics ◽

10.1017/s0022377806005885 ◽

2006 ◽

Vol 72 (06) ◽

pp. 1179 ◽

Cited By ~ 1

Author(s):

M. NAKAMURA ◽

Y. NAKAO

Keyword(s):

Energy Spectrum ◽

Temperature Effect ◽

Neutron Energy ◽

Finite Temperature ◽

Neutron Energy Spectrum ◽

Fusion Plasma ◽

Ion Production

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Space to Air High-Altitude Region Adjoint Neutron Transport

The Journal of Defense Modeling and Simulation Applications Methodology Technology ◽

10.1177/15485129211031669 ◽

2021 ◽

pp. 154851292110316

Author(s):

Zachary W LaMere ◽

Darren E Holland ◽

Whitman T Dailey ◽

John W McClory

Keyword(s):

Energy Spectrum ◽

High Altitude ◽

Neutron Energy ◽

Neutron Transport ◽

Energy Sources ◽

Source Spectrum ◽

Detector Response ◽

Neutron Energy Spectrum ◽

True Source ◽

Adjoint Transport

Neutrons from an atmospheric nuclear explosion can be detected by sensors in orbit. Current tools for characterizing the neutron energy spectrum assume a known source and use forward transport to recreate the detector response. In realistic scenarios the true source is unknown, making this an inefficient, iterative approach. In contrast, the adjoint approach directly solves for the source spectrum, enabling source reconstruction. The time–energy fluence at the satellite and adjoint transport equation allow a Monte Carlo method to characterize the neutron source’s energy spectrum directly in a new model: the Space to High-Altitude Region Adjoint (SAHARA) model. A new adjoint source event estimator was developed in SAHARA to find feasible solutions to the neutron transport problem given the constraints of the adjoint environment. This work explores SAHARA’s development and performance for mono-energetic and continuous neutron energy sources. In general, the identified spectra were shifted towards energies approximately 5% lower than the true source spectra, but SAHARA was able to capture the correct spectral shapes. Continuous energy sources, including real-world sources Fat Man and Little Boy, resulted in identifiable spectra that could have been produced by the same distribution as the true sources as demonstrated by two-dimensional (2D) Kolmogorov–Smirnov tests.

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