@inproceedings{1b1a2b5a87b44005b46677c6f485bb3e,
title = "TORT solutions to the three-dimensional MOX neutron transport benchmark problem, 3-D extension C5G7 MOX",
abstract = "This paper details the results for the OECD/NEA C5G7MOX benchmark obtained using the DOORS code TORT. This benchmark is intended to test modern radiation transport codes' abilities to handle three-dimensional problems with spatial heterogeneity. The problem consists of a four-assembly UO 2 and MOX fuel reflected reactor core in which control rods are inserted to three distinct levels, Unrodded, Rodded A, and Rodded B. A Monte Carlo reference solution was provided with the benchmark. Effective multiplication factor results varied from 0.06\% error for the Unrodded case to 0.17\% and 0.67\% for the Rodded A and Rodded B cases, respectively. The pin power results followed a similar trend. Varying the meshing and angular quadrature refinement did change the results, but not sufficiently to justify the additional computation time.",
keywords = "Benchmark, MOX core calculations, TORT, Three-dimensional, Transport theory",
author = "Klingensmith, \{Jesse J.\} and Azmy, \{Yousry Y.\} and Gehin, \{Jess C.\} and Roberto Orsi",
year = "2004",
language = "English",
isbn = "0894486837",
series = "Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments",
pages = "887--899",
booktitle = "Proceedings of the PHYSOR 2004",
note = "PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments ; Conference date: 25-04-2004 Through 29-04-2004",
}