Abstract
Depletion modeling of advanced reactors with liquid fuel, such as molten salt reactors (MSRs), is complicated by the flowing fuel. Activation and decay of nuclides in the liquid fuel depend on the fluid position, which changes continuously with time. Furthermore, addition and removal of chemical species through processes such as off-gassing, plating, and fueling introduce spatially dependent factors. The general mathematical model for a nuclide n in this type of system is an advection-reaction-decay partial differential equation (PDE), dn/dt = -λn(x, t) - v dn/dx + f, where λ is a decay term, v is the speed attached to the advection term, and f is a reaction term. In actuality, the decay term contains decay physics and reaction physics, but the proportionality to n defines the type of PDE. This paper presents a methodology for solving an advection-reaction-decay system in which solutions are sought along streamlines throughout the flowing fuel system. The solution can provide insight into important operating metrics such as delayed neutron precursor drift and spatially dependent isotope inventory. Although this solution mechanism could prove too computationally intensive for production tools to simulate long-term MSR operations, it can provide benchmark quality solutions for code verification and analysis insights for safeguards and source term applications.
| Original language | English |
|---|---|
| Title of host publication | Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 |
| Publisher | American Nuclear Society |
| Pages | 2133-2144 |
| Number of pages | 12 |
| ISBN (Electronic) | 9781713886310 |
| DOIs | |
| State | Published - 2021 |
| Event | 2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 - Virtual, Online Duration: Oct 3 2021 → Oct 7 2021 |
Publication series
| Name | Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 |
|---|
Conference
| Conference | 2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 |
|---|---|
| City | Virtual, Online |
| Period | 10/3/21 → 10/7/21 |
Funding
This work was supported by the US Department of Energy Office of Nuclear Energy’s Material Protection, Accounting, and Control Technologies Campaign and the Nuclear Regulatory Commission’s Non-Light Water Reactor analysis. ∗Notice: This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan)
Keywords
- ORIGEN
- depletion
- molten salt reactors
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