Multispecies Diffusion Capability For The AMP Nuclear Fuel Performance Code (LANL Milestone M31MS060301 Final Report)

Dilts, Gary A.¹ 

[1] Los Alamos National Laboratory

关键词: BURNUP;    DIFFUSION;    FAST REACTORS;    LANL;    NUCLEAR FUELS;    ORNL;    PERFORMANCE;    PHASE DIAGRAMS;    REACTORS;    SIMULATION;    SOLVENTS;    VALIDATION;    VERIFICATION;   

DOI  :  10.2172/1038124
RP-ID  :  LA-UR-12-20289
PID  :  OSTI ID: 1038124
Others  :  TRN: US1201891

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来源: SciTech Connect

【 摘 要 】

This work addresses only diffusion. The contact solver in AMP was not sufficiently developed this year to attempt treatment of species contact. A cylindrical tensor diffusion coefficient model was added to the AMP code, with the KHHS model [1] implemented into the AMP material library as a specific example. A cylindrical tensor diffusion operator manufactured solution verification example was coded. Before meeting the full text of the milestone task, it remains to: (1) code and run a cylindrical tensor diffusion solver manufactured solution (2) code and run the validation example of [1] (3) document results. These are dependent on developing new capabilities for the AMP code requiring close collaboration with the AMP team at ORNL. The model implemented provides a good intermediate first step toward a general multi-species solver. The multi-species capability of the AMP nuclear fuel code [2] is intended to allow the modeling of radiation-driven redistribution of various elements through solid metal nuclear reactor fuels. The initial model AMP provides for U-Pu-Zr fuels is based on the analysis of the Integral Fast Reactor (IFR) fuel development program experiment X419 post-irradiation data described in [1], referred to here as the KHHS model. This model may be specific to that experiment, but it was thought to provide a good start for the AMP code, because it (1) is formulated at the engineering scale, (2) decouples the species from each other, (3) predetermines the phase boundaries so that reference to a phase diagram is not needed, and (4) one of the authors (Hayes) was the NEAMS Fuels IPSC manager for FY11. The KHHS model is formulated for radial fluxes as little axial redistribution is seen experimentally. As U-Pu-Zr fuel is irradiated, the constituents migrate to form three annular regions. The center region is Zr-enriched and U-depleted, the middle region is Zr-depleted and U-enriched, and the outer region is Zr-enriched and U-depleted. The Pu concentration stays roughly constant throughout with slight enrichment in the center and depletion near the surface. Pu acts as a solvent for the mixture. The experiment was only run to 1.9% burnup, so the model is not at this time applicable to the high-burnup scenarios that the AMP code is intended to eventually model.