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Neutronics in Fusion: Difference between revisions

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[https://en.wikipedia.org/wiki/Neutron_transport Neutron transport] in [https://en.wikipedia.org/wiki/Nuclear_fusion fusion] describes the behavior and interactions of neutrons produced during fusion reactions. In [[Nuclear fusion]] systems, especially in deuterium–tritium reactions, high-energy neutrons (about 14.1 MeV) are generated in large numbers. These neutrons carry most of the fusion energy and interact with the surrounding materials, where their energy is deposited through scattering and nuclear reactions. Neutronics analysis is therefore essential for predicting energy deposition, material damage, radiation shielding requirements, and tritium breeding performance. Understanding neutronics is a key aspect of designing safe, efficient, and sustainable fusion reactors.
[https://en.wikipedia.org/wiki/Neutron_transport Neutrons] generated in [https://en.wikipedia.org/wiki/Nuclear_fusion fusion reactions] carry most of the fusion energy and interact with surrounding materials <ref name="NeutronTransport"/><ref name="NuclearFusion"/>. In fusion systems, especially deuterium–tritium reactions, high-energy neutrons (about 14.1 MeV) are produced in large numbers. Their energy is deposited into surrounding materials through scattering and nuclear reactions. Neutronics analysis is therefore essential for predicting energy deposition, material damage, radiation shielding requirements, and tritium breeding performance. Understanding neutronics is a key aspect of designing safe, efficient, and sustainable fusion reactors.




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'''Note:''' Because tritium is extremely rare in nature (half-life ≈ 12.3 years), fusion reactors are initially supplied with tritium from existing stockpiles (primarily from CANDU fission reactors), after which tritium is continuously bred from lithium within the reactor blanket to sustain operation<ref name="TritiumCANDU"/>.
'''Note:''' Because tritium is extremely rare in nature (half-life ≈ 12.3 years), fusion reactors are initially supplied with tritium from existing stockpiles (primarily from CANDU fission reactors), after which … tritium is continuously bred from lithium within the [[Breeding blanket]] to sustain reactor operation <ref name="TritiumCANDU"/>.
 


== Neutron Modeling in Plasma Codes ==
== Neutron Modeling in Plasma Codes ==


Neutronics simulation plays a fundamental role in the advancement of nuclear fusion by supporting reactor design, safety assessment, and material optimization. The following plasma modeling codes are used to predict fast-ion behavior and fusion-born neutron emission in tokamak and stellarator plasmas, providing neutron source distributions for transport simulations and diagnostic design.
Neutronics simulation plays a fundamental role in the advancement of nuclear fusion by supporting reactor design, safety assessment, and material optimization. The following [[Plasma simulation]] and fast-ion modeling codes are used to predict fast-ion behavior and fusion-born neutron emission in [[Tokamak]] and [[Stellarator]] plasmas, providing neutron source distributions for transport simulations and diagnostic design.


{| class="wikitable"  
{| class="wikitable"  
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| Monte Carlo orbit-following codes for fast ions in tokamaks and stellarators; predict localized neutron emission patterns to aid diagnostic design and calibration <ref name="ASCOTneutron"/><ref name="ASCOTfurth"/>
| Monte Carlo orbit-following codes for fast ions in tokamaks and stellarators; predict localized neutron emission patterns to aid diagnostic design and calibration <ref name="ASCOTneutron"/><ref name="ASCOTfurth"/>
|}
|}


== Neutron Modeling Using Monte Carlo Neutronics Codes ==
== Neutron Modeling Using Monte Carlo Neutronics Codes ==
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|}
|}


= Neutron Detectors in Fusion Tokamaks =
== Neutron Detectors in Fusion Tokamaks ==


The progress in neutron detectors for fusion devices has enabled increasingly precise measurements of neutron flux, energy spectra, and spatial emission profiles. Advances in detector technology and modeling now allow researchers to better assess key plasma parameters, including fusion power, ion temperature, and fuel composition.
The progress in neutron detectors for fusion devices has enabled increasingly precise measurements of neutron flux, energy spectra, and spatial emission profiles. Advances in detector technology and modeling now allow researchers to better assess key plasma parameters, including fusion power, ion temperature, and fuel composition.
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= Useful GitHub Repositories for Neutronics in Nuclear Fusion =
== Useful GitHub Repositories for Neutronics in Nuclear Fusion ==


Several GitHub repositories provide tools and workflows that are highly valuable for neutronics development in fusion research:
Several GitHub repositories provide tools and workflows that are highly valuable for neutronics development in fusion research:
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# '''Fusion-Power-Plant-Framework / tokamak-neutron-source''' – A Python package to create an arbitrary parametric tokamak neutron source for use with Monte Carlo radiation transport codes such as OpenMC and MCNP. It allows specification of plasma profiles (ion density, temperature, equilibrium) and exports source definitions for neutronics simulations. (GitHub: https://github.com/Fusion-Power-Plant-Framework/tokamak-neutron-source)
# '''Fusion-Power-Plant-Framework / tokamak-neutron-source''' – A Python package to create an arbitrary parametric tokamak neutron source for use with Monte Carlo radiation transport codes such as OpenMC and MCNP. It allows specification of plasma profiles (ion density, temperature, equilibrium) and exports source definitions for neutronics simulations. (GitHub: https://github.com/Fusion-Power-Plant-Framework/tokamak-neutron-source)


= See Also =
== See Also ==
* [[Nuclear fusion]]
* [[Nuclear fusion]]
* [[Breeding blanket]]
* [[Breeding blanket]]
* [[Plasma simulation]]
* [[Plasma simulation]]


= External links =
== External links ==
* [https://link.springer.com/book/10.1007/978-981-10-5469-3 Neutronics in Fusion Reactors – Springer Book]
* [https://link.springer.com/book/10.1007/978-981-10-5469-3 Fusion Neutronics – Springer Book]
* [https://en.wikipedia.org/wiki/Nuclear_fusion Nuclear Fusion – Wikipedia article]
* [https://en.wikipedia.org/wiki/Nuclear_fusion Nuclear Fusion – Wikipedia article]
* [https://www.iter.org/machine/supporting-systems/tritium-breeding Tritium Breeding – ITER]
* [https://www.iter.org/machine/supporting-systems/tritium-breeding Tritium Breeding – ITER]
* [https://www.tandfonline.com/doi/full/10.1080/15361055.2022.2141528 Advancing Methods for Fusion Neutronics: An Overview of Workflows and Nuclear Analysis Activities at UKAEA]
* [https://link.springer.com/book/10.1007/978-981-13-6520-1 Neutronics of Advanced Nuclear Systems]
* [https://doi.org/10.1016/S0920-3796(00)00160-5 Neutronics on inertial fusion reactors]


= References =
== References ==
<references>
<references>
<ref name="NeutronTransport">
"Neutron transport," Wikipedia, https://en.wikipedia.org/wiki/Neutron_transport
</ref>
<ref name="NuclearFusion">
"Nuclear fusion," Wikipedia, https://en.wikipedia.org/wiki/Nuclear_fusion
</ref>


<ref name="BreedingBlanket">
<ref name="BreedingBlanket">
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<ref name="TRANSPneutron">
<ref name="TRANSPneutron">
A. Sperduti et al., “Validation of neutron emission and neutron energy spectrum calculations on a Mega Ampere Spherical Tokamak,” *Plasma Physics and Controlled Fusion*, vol. 63, no. 1, 2021. https://doi.org/10.1088/1361-6587/abca7d :contentReference[oaicite:0]{index=0}
A. Sperduti et al., “Validation of neutron emission and neutron energy spectrum calculations on a Mega Ampere Spherical Tokamak,” *Plasma Physics and Controlled Fusion*, vol. 63, no. 1, 2021. https://doi.org/10.1088/1361-6587/abca7d  
</ref>
</ref>


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<ref name="NUBEAM">
<ref name="NUBEAM">
A. Pankin et al., “The tokamak Monte Carlo fast ion module NUBEAM in the National Transport Code Collaboration library,” *Computer Physics Communications*, vol. 159, no. 3, 2004. https://doi.org/10.1016/j.cpc.2003.11.002 :contentReference[oaicite:1]{index=1}
A. Pankin et al., “The tokamak Monte Carlo fast ion module NUBEAM in the National Transport Code Collaboration library,” *Computer Physics Communications*, vol. 159, no. 3, 2004. https://doi.org/10.1016/j.cpc.2003.11.002
</ref>
</ref>


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<ref name="MCNP">
<ref name="MCNP">
C. J. Werner (ed.), *MCNP User’s Manual – Code Version 6.2*, Los Alamos National Laboratory, LA-UR-17-29981. https://mcnpx.lanl.gov/ :contentReference[oaicite:2]{index=2}
C. J. Werner (ed.), *MCNP User’s Manual – Code Version 6.2*, Los Alamos National Laboratory, LA-UR-17-29981. https://mcnpx.lanl.gov/  
</ref>
</ref>


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<ref name="Geant4">
<ref name="Geant4">
S. Agostinelli et al., "GEANT4 — a simulation toolkit," *Nuclear Instruments and Methods in Physics Research Section A*, vol. 506, pp. 250–303, 2003. https://doi.org/10.1016/S0168-9002(03)01368-8 :contentReference[oaicite:0]{index=0}
S. Agostinelli et al., "GEANT4 — a simulation toolkit," *Nuclear Instruments and Methods in Physics Research Section A*, vol. 506, pp. 250–303, 2003. https://doi.org/10.1016/S0168-9002(03)01368-8  
</ref>
</ref>


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</references>
</references>
[[Category:Neutronics]]
[[Category:Software]]
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