This paper details the results far 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 UO2 and MOX fuel reflected reactor care 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.
TORT Solutions to the Three-Dimensional MOX Neutron Transport Benchmark Problem, 3-D Extension C5G7 MOX
Orsi, R.;
2004-04-25
Abstract
This paper details the results far 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 UO2 and MOX fuel reflected reactor care 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.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
