Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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MONTE CARLO METHOD EXTENDED TO HEAT TRANSFER PROBLEMS WITH NON-CONSTANT TEMPERATURE AND CONVECTION BOUNDARY CONDITIONS

  • Cho, Bum-Hee (Korea Advanced Institute of Science and Technology) ;
  • Cho, Nam-Zin (Korea Advanced Institute of Science and Technology)
  • Published : 2010.02.28
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Abstract

The Monte Carlo method for solving heat conduction problems [1-3] is extended for non-constant temperature boundary conditions in this study. The new method can treat problems with any given non-constant boundary temperatures, including heat convection problems with non-constant fluid bulk temperature. A set of problems, particularly the heat transfer problem in a pebble fuel, is analyzed by this new method. In addition, a new method to reduce the statistical errors in kernel fuel regions is introduced when the Monte Carlo method is applied to a pebble fuel.

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References

  1. Jun Shentu, Sunghwan Yun, and Nam Zin Cho, "A Monte Carlo Method for Solving Heat Conduction Problems with Complicated Geometry", Nuclear Engineering and Technology, Vol. 39, 2007, pp. 207. https://doi.org/10.5516/NET.2007.39.3.207
  2. Jae Hoon Song and Nam Zin Cho, "An Improved Monte Carlo Method Applied to the Heat Conduction Analysis of a Pebble with Dispersed Fuel Particles", Nuclear Engineering and Technology, Vol. 41, 2009, pp. 279. https://doi.org/10.5516/NET.2009.41.3.279
  3. Jae Hoon Song and Nam Zin Cho, "Temperature Distnbutions in a Pebble with Dispersed Fuel Particles Calculated by Monte Carlo Method", Transactions of American Nuclear Society, Vol. 98, 2008, pp. 443.
  4. H.S. Carslaw, and J.c. Jaeger, Conduction of Heat in Solids, 2nd ed., Oxford, 1959.
  5. Hui Yu and Nam Zin Cho, "Comparison of Monte Carlo Simulation Models for Randomly Distributed Particle Fuels in VHTR Fuel Elements", Transactions of American Nuclear Society, Vol. 95, 2006, pp. 719.
  6. Jae Hoon Song and Nam Zin Cho, "HEATON -A Monte Carlo Code for Thermal Analysis of Pebble Fuels in VHTR-", Nuclear Reactor Analysis and Particle Transport Laboratory Internal Report, NURAPT-2007-01, KAlST, August 2007.
  7. Nam Zin Cho, Hui Yu, and Jong Woon Kim, "Two-Temperature Homogenized Model for Steady-State and Transient Thermal Analyses of a Pebble with Distributed Fuel Particles", Annals of Nuclear Energy, Vol. 36, 2009, pp. 448; see also "Corrigendum to: Two-Temperature Homogenized Model for Steady-State and Transient Thermal Analyses of a Pebble with Distributed Fuel Particles," Annals of Nuclear Energy, Vol. 37, 2010, pp. 293. https://doi.org/10.1016/j.anucene.2009.10.016