In next-step fusion tokamaks such as SPARC and ITER, achieving high levels of scrape-off-layer power dissipation will be essential to protect the divertor while maintaining good core plasma performance. The Lengyel model for power dissipation is easy to interpret and fast enough to incorporate into plasma control and scoping tools, but it systematically overestimates the impurity concentration required to reach detachment by a factor of relative to experiments and higher-fidelity simulations. In this work, we extended the Lengyel model to match the semi-empirical Kallenbach scaling, which successfully describes detachment access on several operating tokamaks. We found that we can reproduce the experimental scaling by accounting for cross-field transport in the divertor, power and momentum loss due to neutral ionization close to the divertor target and turbulent broadening of the upstream heat flux channel. These corrections cause the impurity concentration required for detachment to decrease faster than , reproducing the scalings found in experiment. The model also quantitatively reproduces the impurity concentration needed to reach detachment in experiment, demonstrating that the extended Lengyel model can be used as a simple, accurate model for detachment access.
This paper presents an improved model for predicting the conditions required to achieve detachment in fusion tokamaks like SPARC and ITER. The model accounts for key physical processes, such as cross-field transport and power/momentum loss due to neutral ionization, to better match experimental observations. This allows for more accurate predictions of the impurity concentration needed to reach detachment, which is crucial for protecting the divertor while maintaining good core plasma performance.