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Neutronics in Fusion: Difference between revisions

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Neutronics in fusion deals with the behavior and effects of neutrons produced during fusion reactions. In 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.
 


== Fusion Reactions ==
== Fusion Reactions ==
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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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| [https://github.com/openmc-dev/openmc OpenMC]
| [https://github.com/openmc-dev/openmc OpenMC]
| High-fidelity neutron transport in complex 3D fusion geometries; neutron diagnostics scoping; activation analysis; uncertainty and sensitivity studies <ref name="OpenMC"/>
| High-fidelity neutron transport in complex 3D fusion geometries; neutron diagnostics scoping; activation analysis; uncertainty and sensitivity studies <ref name="OpenMC"/>
|-
| [https://geant4.web.cern.ch Geant4]
| Detector and diagnostic modeling; energy deposition and shielding studies in complex 3D geometries <ref name="Geant4"/>
|}
|}


 
== 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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! Numerical Tools
! Numerical Tools
|-
|-
| Neutron Counters and Flux Monitors<ref name="Counters"/>
| Neutron Counters and Flux Monitors<ref name="Cameras"/>
| Neutrons induce charged particle reactions in gas or fissile material
| Neutrons induce charged particle reactions in gas or fissile material
| Neutron flux / total yield
| Neutron flux / total yield
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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]]
* [[TECNO FUS]]
* [[Breeding blanket]]
* [[Breeding blanket]]
* [[Fusion databases]]
* [[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>


<ref name="FIDASIM">
<ref name="FIDASIM">
B. Geiger, L. Stagner, W. W. Heidbrink et al., “Progress in modelling fast-ion D-alpha spectra and neutral particle analyzer fluxes using FIDASIM,” *Plasma Physics and Controlled Fusion*, 2020. https://doi.org/10.1088/1361-6587/abca7d
B. Geiger, L. Stagner, W. W. Heidbrink et al., “Progress in modelling fast-ion D-alpha spectra and neutral particle analyzer fluxes using FIDASIM,” *Plasma Physics and Controlled Fusion*, 2020. https://iopscience.iop.org/article/10.1088/1361-6587/aba8d7
</ref>
</ref>


<ref name="ASCOTneutron">
<ref name="ASCOTneutron">
H. Weisen, P. Sirén, J. Varje & JET Contributors, “Comparison of JET-C DD neutron rates independently predicted by the ASCOT and TRANSP Monte Carlo heating codes,” *Nuclear Fusion*, vol. 62, 016017, 2022. https://doi.org/10.1088/1741-4326/ac1d3f
H. Weisen, P. Sirén, J. Varje & JET Contributors, “Comparison of JET-C DD neutron rates independently predicted by the ASCOT and TRANSP Monte Carlo heating codes,” *Nuclear Fusion*, vol. 62, 016017, 2022. https://iopscience.iop.org/article/10.1088/1741-4326/ac3be4
</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>


<ref name="Serpent">
<ref name="Serpent">
J. Leppänen et al., *The Serpent Monte Carlo Code: Status, Development and Applications in Fusion Neutronics*, *Annals of Nuclear Energy*, (published articles on Serpent include: https://doi.org/10.1016/j.anucene.2014.07.018)
J. Leppänen et al., "The Serpent Monte Carlo Code: Status, Development and Applications in Fusion Neutronics", *Annals of Nuclear Energy*, (published articles on Serpent include: https://www.sciencedirect.com/science/article/abs/pii/S0306454914004095)
</ref>
</ref>


<ref name="OpenMC">
<ref name="OpenMC">
P. K. Romano et al., “OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development,” *Annals of Nuclear Energy* (recommended citation) and official OpenMC docs at https://docs.openmc.org/ :contentReference[oaicite:3]{index=3}
P. K. Romano et al., “OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development,” *Annals of Nuclear Energy* (recommended citation) and official OpenMC docs at https://docs.openmc.org/ https://www.sciencedirect.com/science/article/abs/pii/S030645491400379X?via%3Dihub
</ref>
</ref>


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</ref>
</ref>


* <ref name="Counters">Springer, “Neutron Diagnostics for Tokamak Plasma”, 2018. https://link.springer.com/article/10.1007/s10894-018-0195-9</ref>
<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
</ref>
 
 
* <ref name="Activation">Springer, “Neutron Activation Techniques in Fusion Devices”, 2018. https://link.springer.com/article/10.1007/s10894-018-0183-0</ref>
* <ref name="Activation">Springer, “Neutron Activation Techniques in Fusion Devices”, 2018. https://link.springer.com/article/10.1007/s10894-018-0183-0</ref>
* <ref name="Spectrometers">ArXiv, “Proton Recoil Neutron Spectrometers for Tokamak Diagnostics”, 2019. https://arxiv.org/abs/1902.07633</ref>
* <ref name="Spectrometers">ArXiv, “Proton Recoil Neutron Spectrometers for Tokamak Diagnostics”, 2019. https://arxiv.org/abs/1902.07633</ref>
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</references>
</references>
[[Category:Neutronics]]
[[Category:Software]]
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