Methods and Tools to allow molecular flow simulations to be coupled to higher level continuum descriptions of flows in porous/fractured media and aerosol/dust dynamics

Technical Report · Thu Apr 09 00:00:00 EDT 2015

DOI:https://doi.org/10.2172/1201742· OSTI ID:1201742

Loyalka, Sudarshan ^[1]

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1. Univ. of Missouri, Columbia, MO (United States)

The purpose of this project was to develop methods and tools that will aid in safety evaluation of nuclear fuels and licensing of nuclear reactors relating to accidents.The objectives were to develop more detailed and faster computations of fission product transport and aerosol evolution as they generally relate to nuclear fuel and/or nuclear reactor accidents. The two tasks in the project related to molecular transport in nuclear fuel and aerosol transport in reactor vessel and containment. For both the tasks, explorations of coupling of Direct Simulation Monte Carlo with Navier-Stokes solvers or the Sectional method were not successful. However, Mesh free methods for the Direct Simulation Monte Carlo method were successfully explored.These explorations permit applications to porous and fractured media, and arbitrary geometries.The computations were carried out in Mathematica and are fully parallelized. The project has resulted in new computational tools (algorithms and programs) that will improve the fidelity of computations to actual physics, chemistry and transport of fission products in the nuclear fuel and aerosol in reactor primary and secondary containments.

• Research Organization: Univ. of Missouri, Columbia, MO (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE). Nuclear Energy University Programs (NEUP)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1201742
• Report Number(s): DOE/NEUP-10-964; 10-964; TRN: US1500410
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
AEROSOLS
NUCLEAR FUELS
MONTE CARLO METHOD
FISSION PRODUCTS
POROUS MATERIALS
COMPUTERIZED SIMULATION
TRANSPORT
REACTOR ACCIDENTS
ALGORITHMS
DUSTS
REACTORS
SAFETY ANALYSIS
CHEMISTRY
RADIONUCLIDE MIGRATION
FLUID MECHANICS
PROGRAMMING