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Tritium Calculation for MSR

UMass Lowell Spring 2021
Dept. of Chemical Engineering, Nuclear Program
Engy-5310: Computational Continuum Transport Phenomena

View the project on NBViewer: NBViewer

Run the project on Binder: Binder

Anthony G. Bowers, and Prof. Subash L. Sharma
Dept. of Chemical Engineering (Nuclear Energy)
University of Massachusetts Lowell, USA

Problem domain sketch.

Results.

References:

  • [1] V. F. de Almeida, Engy-5310: Computational Continuum Transport Phenomena, University of Massachusetts Lowell, Dept. of Chemical Engineering (Nuclear Energy Program).
  • [2] Multiphysics Object-Oriented Simulation Environment (MOOSE)
  • [3] Stempien D. John, “Tritium Transport, Corrosion, and Fuel Performance Modeling in Fluoride Salt-Cooled High-Temperature Reactor (FHR)”. Massachusetts Institute of Technology. PDF. June 2017
  • [4] R. Serrano-Lópeza, J. Fraderaa, S. Cuesta-Lópeza. “Molten salts database for energy applications”. PDF. September 2014.