Neutronics in Fusion: Difference between revisions
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== 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 | 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. | ||
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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 Neutronics in Fusion Reactors – 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] | ||
= References = | == References == | ||
<references> | <references> | ||