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Leveraging Deuterium to Increase Neutron Production in an Inertial Fusion Energy Power Plant Concept: A MCNP6.2 Simulation Analysis
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DOI：10.1080/15361055.2026.2629207.png)
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Abstract
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A study of an inertial fusion energy (IFE) power plant concept, HYLIFE-III, is performed to assess the potential to increase neutron yield through target modifications. The study examines Xcimer Energy Corporation's proposed HYLIFE-III chamber and hybrid IFE target concepts using the radiation transport code MCNP version 6.2. Furthermore, two key design features are modified to exploit the strong (n,2n) cross section of deuterium as a substitute for beryllium (n,2n) production within the chamber concept. Specifically, this study applies a thickened deuterated carbon (CD) ablator layer to the capsule wall of the IFE target and increases the deuterium/tritium fuel ratio as high as 70:30. The increased neutron production from this added deuterium is sufficient to enable FLiNaK (LiF-NaF-KF) to achieve a tritium breeding ratio greater than 1, identifying the potential for an IFE chamber concept that does not require beryllium.
Keywords:
Deuterium
inertial fusion energy
MCNP
tritium breeding
FLiNaK
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