Toward a high-fidelity tritium transport modeling for retention and permeation experiments

Shimada, Masashi; Simon, Pierre-Clément A.; Icenhour, Casey T.; Singh, Gyanender

doi:10.1016/j.fusengdes.2024.114438

Toward a high-fidelity tritium transport modeling for retention and permeation experiments

Journal Article · Sat Apr 13 00:00:00 EDT 2024 · Fusion Engineering and Design

DOI:https://doi.org/10.1016/j.fusengdes.2024.114438· OSTI ID:2349489

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Idaho National Laboratory (INL), Idaho Falls, ID (United States)

We report Tritium Migration Analysis Program version 8 (TMAP8), the latest version of TMAP, was developed within the framework of the Multiphysics Object-Oriented Simulation Environment (MOOSE). Created at Idaho National Laboratory (INL), MOOSE is an open-source, dimension-agnostic, fully coupled, and fully implicit multiphysics platform featuring massively parallel computation capabilities. Using TMAP8, tritium transport in a divertor monoblock was analyzed to elucidate the effects of pulsed operation (up to fifty 1,600 s plasma discharge and cool-down cycles) on the tritium in-vessel inventory source term and ex-vessel release term (i.e., tritium retention and permeation) for safety analysis. With its built-in Message Passing Interface capability, TMAP8 can, in under 2 h, simulate tritium transport in three different layered materials (i.e., tungsten, copper, and copper-chromium-zirconium alloy) in 2D geometry, using a single device/computer with 10 cores. The MOOSE-based TMAP8 code can leverage other MOOSE tools developed under the Nuclear Energy Advanced Modeling and Simulation program to perform tritium and thermal transport in complex geometries and multiphysics environments. And via its massively parallel computation, MOOSE will enable the fusion pilot plant designers to conduct high-fidelity multiphysics modeling for the design of the divertor and blanket systems as well as for the safety analysis.

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 2349489

Alternate ID(s):: OSTI ID: 2336858

Report Number(s):: INL/JOU-24-76370-Rev000

Journal Information:: Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Journal Issue: - Vol. 203; ISSN 0920-3796

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Toward a high-fidelity tritium transport modeling for retention and permeation experiments

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