EPJ Web of Conferences
Volume 106, 2016ISRD 15 – International Symposium on Reactor Dosimetry
|Number of page(s)||9|
|Section||Transport Calculations (Neutron and Gamma-Ray) and Modeling|
|Published online||03 February 2016|
Application of TITAN for Simulation of Particle Streaming in a Duct
1 Virginia Tech, 900 N. Glebe Rd., Arlington, Virginia, USA
2 Georgia Tech, 770 State St., Atlanta, Georgia, USA
a Corresponding author: firstname.lastname@example.org
Published online: 3 February 2016
The TITAN hybrid deterministic transport code is applied to the simulation of particle streaming in a nuclear power plant duct. A simple model is used consisting of a concrete duct emerging from the pressure vessel with an isotropic surface source with a U-235 fission spectrum located at the pressure vessel end. Multiple methods of simulating the duct using the TITAN code are considered to demonstrate the flexibility of the code and the advantages of TITAN's algorithms. These methods include a discrete ordinates (SN) calculation, a characteristics method calculation, and the use of a fictitious quadrature set with simplified ray-tracing. The TITAN code's results are compared with MCNP5 solutions. While all TITAN solutions are obtained in a shorter computation time than the MCNP5 solution, the TITAN solution with the fictitious quadrature set shows the largest speedup.
© Owned by the authors, published by EDP Sciences, 2016
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