Integrated models to study the impact of ELMs and disruptions on lithium in the NSTX divertor

Efficient Monte Carlo Simulation of Heat Conduction Problems for Integrated Multi-Physics Applications

“…The dense cold plasma is located in the negative part of the computational domain and the hot rarefied layer is located in the positive part of the domain as shown in Figure 8. This situation corresponds to what is called the ''plasma shielding'' effect, where the evaporated Li layer shields the rest of the Li component from the incident-disrupting plasma [32]. The benchmarking simulations showed good agreement between our Monte Carlo method and the predictions of the previously used implicit scheme.…”

“…We also compared our simulations with results calculated using both explicit and implicit methods and found good agreement. Application of the method to more realistic physical problems is also provided to simulate heat conduction of plasma in tokamak fusion devices [32]. Multidimensional expansion of this method is also developed and tested.…”

“…In real plasma, the transport coefficients depend nonlinearly on the local temperature, and the behavior=stability of the numerical methods under these conditions is important. For this purpose we calculated, as an example, the heat transport between separate Li plasma layers in a tokamak machine operating with liquid lithium as plasma-facing component during a plasma disruption event [32]. The dense cold plasma is located in the negative part of the computational domain and the hot rarefied layer is located in the positive part of the domain as shown in Figure 8.…”

Multi‐level model of radiation transport in inhomogeneous plasma

“…Somewhat similar effects are of concern in laser‐based techniques of the first wall in situ diagnostics where the correct determination of radiation power from dense plasma produced by laser radiation is important for the estimation of hydrogen content in the wall. Radiation trapping can also be important for tokamaks with lithium walls …”

“…Radiation trapping can also be important for tokamaks with lithium walls. [9] The SOLPS code is one of the most used codes for the modelling of edge plasma in tokamaks. [10] The SOLPS-ITER version is officially used by ITER as a development tool for the divertor construction.…”