NRIC Virtual Test Bed: tritium in a divertor monoblock during pulsed operation (TMAP8).
How does pulsed tokamak operation change the tritium retained inside an ITER-like tungsten/copper/CuCrZr divertor monoblock and the tritium that permeates through to the coolant tube, when heat conduction and hydrogen-isotope diffusion with trapping are solved together in 2D?
A transient 2D finite-element demonstration published in the NRIC Virtual Test Bed: coupled heat conduction and tritium transport with trapping and release through three solid materials over up to fifty 1,600 s plasma cycles, reproducing figures from a 2024 Fusion Engineering and Design paper. It is tagged as a demonstration, intended as a safety-analysis input rather than a validated prediction.
Relationship to fusion
Magnetic-confinement fusion: an ITER-like tokamak divertor monoblock under pulsed heat and tritium flux. For an inertial-fusion chamber this is analogous only, not validating: the shared physics is hydrogen-isotope diffusion, trapping and permeation in metals under cyclic thermal loads, but geometry, materials, plasma-contact mechanism, flux magnitudes and time scales differ.
A specific published external example has been documented.
What stands between this and a Morton reproduction
- Requires a TMAP8 build on MOOSE; Morton Labs has not built or run this case.
- One TMAP8 input file (divertor_monoblock.i) with the mesh generated in-file: 36 sectors, radii 6, 7.5 and 8.5 mm, 28 mm pitch, half domain with symmetry
- Plasma cycle: 100 s ramp-up, 400 s flat-top, 100 s ramp-down, 1,000 s dwell; end time 8.0e4 s
- Heat flux 10 MW/m2 at flat-top on the plasma-facing surface; coolant wall temperature 552 K at flat-top and 300 K in dwell
- Tritium surface flux of 5.0e20 m-2 s-1 entering the first mesh layer (0.1 % of the incident flux)
- Material diffusivities, solubilities, trap densities and detrapping energies for tungsten, copper and CuCrZr
- Run per the VTB instructions: tmap8-opt -i divertor_monoblock.i
- Time histories of mobile, trapped and total tritium inventory in each material
- Tritium permeation flux through the coolant-tube wall and release flux at the plasma-facing surface
- Temperature at the top surface and at the tube wall; field output at selected cycle times
- Figures reproducing the 2024 paper's temperature, inventory and field plots
- 2D cross-section with mirror symmetry; coolant replaced by a prescribed wall temperature and near-zero tritium concentration
- Plasma implantation and surface recombination simplified to a fixed surface flux into the first mesh layer
- One trap population per material with constant density; relatively low detrapping energies chosen to keep run time down
- Chemical-potential equilibrium at material interfaces; no neutron damage, transmutation or thermomechanics
- The VTB page notes a mismatch between some documented detrapping energies and the active input values
- TMAP8
- devel branch (no tagged releases) github.com ↗
- MOOSE
- Virtual Test Bed submodule github.com ↗
- Virtual Test Bed repository
- devel HEAD 33898f60853e49773cd119cf93140e1b31a690c6 (2026-10-08) github.com ↗
This case was written by Morton Labs from public sources and last checked on 2026-10-10. Spotted an error, or want something changed or removed? Email zach@mortonlabs.ai with the page address.
Sources checked for this page (5)
- VTB divertor monoblock page — Physics, inputs, outputs, assumptions, runtime statement
- VTB example directory — Input file and test specification
- VTB LICENSE — CC-BY-4.0
- Crossref record for Shimada et al. 2024 — Source paper details
- Crossref record for Giudicelli et al. 2023 — VTB overview paper the repository asks users to cite