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Dingkang, Zhang; Farzad, Rahnema; Dumitru, Serghiuta
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)2010
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)2010
AbstractAbstract
[en] In this paper, three states of a postulated stylized 4x4 fuel channels region of a Candu core were developed to test the coarse mesh transport code COMET. The benchmark problem consists of 192 fuel bundles in 16 fuel channels with 8 different burnups. The model includes a total of 6 adjuster rods of the same type perpendicular to the fuel channels and located on three axial locations. COMET calculations were performed based a pre-computed two-group response function library, which was generated using a modified version of the Monte Carlo code MCNP. In these calculations, the incoming/outgoing angular currents on the bounding surfaces of each coarse mesh were expanded in terms of tensor products of Legendre polynomials. The orders of expansion in the two spatial variables and the polar and azimuth angles were 4, 4, 2 and 2, respectively. Reference solutions were computed by using MCNP5 and a two group cross section library generated with lattice depletion transport code HELIOS. The comparison showed the global eigenvalue predicated by COMET agrees very well with the MCNP reference solution (within 50 pmc). For the pin-fission density distribution of 7104 fuel pins, the maximum and average relative difference are about 2% and 0.9%, respectively. (authors)
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2010; 11 p; American Nuclear Society - ANS; La Grange Park, Illinois (United States); PHYSOR 2010: Advances in Reactor physics to Power the Nuclear Renaissance; Pittsburgh, PA (United States); 9-14 May 2010; ISBN 978-0-89448-079-9;
; Country of input: France; 6 refs.

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