Explicit modeling of particle fuel for the very-high temperature gas-cooled reactor

Transactions of the American Nuclear Society

Volumn 92, Issue , 2005, Pages 236-238

  Ji, Wei ^a   Conlin, Jeremy L ^a   Martin, William R ^a   Lee, John C ^a   Brown, Forrest B ^b  

^a UNIVERSITY OF MICHIGAN   (United States)

^b LOS ALAMOS NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 33244465823     PISSN: 0003018X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (8)

1. F. B. Brown, "MCNP - A General Monte Carlo N-Particle Transport Code, Version 5", LA-UR-03-1987, Los Alamos National Laboratory (2003).
2. F. B. Brown and W. R. Martin, "Stochastic Geometry Capability in MCNP5 for the Analysis of Particle Fuel," Annals of Nuclear Energy 31, (November 2004).
3. W. Ji, J. L. Conlin, W. R. Martin, and J. C. Lee, "Reactor Physics Analysis of the VHTGR Core," Trans. Am. Nucl. Soc. 91, 556-558, Washington, DC (November 2004).
4. F. B. Brown, W. R. Martin, W. Ji, J. L. Conlin and J. C. Lee "Stochastic Geometry and HTGR Modeling with MCNP5," submitted for presentation to ANS M&C Conference, Chattanooga, TN (April 2005).
5. P. E. MacDonald, et al., "NGNP Preliminary Point Design - Results of the Initial Neutronics and Thermal-Hydraulic Assessments During FY-03", INEEL/EXT-03-00870 Rev. 1, Idaho National Engineering and Environmental Laboratory (2003).
6. Murata, I., Mori, T., and Nakagawa, M., "Continuous Energy Monte Carlo Calculations of Randomly Distributed Spherical Fuels in High-Temperature Gas-Cooled Reactors Based on a Statistical Geometry Model," Nucl. Sci. Eng. 123, 96-109 (1996).
7. F. B. Brown and W. R. Martin, "Stochastic Geometry in MCNP5", Trans. Am. Nucl. Soc. 91, 171-173, Washington, DC (November 2004).
8. Widom, S., "Random Sequential Addition of Hard Spheres to a Volume," J. Chem. Phy. 44, 3888-3894 (1966).