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Lee, Deokjung
Computational Reactor physics & Experiment Lab.
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Comparative neutronics analysis of dimple S06 benchmark

Author(s)
Kim, WonkyeongPark, JinsuLee, DeokjungKozlowski, Tomasz
Issued Date
2015-03-29
URI
https://scholarworks.unist.ac.kr/handle/201301/36945
Citation
5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015, pp.416 - 431
Abstract
The DIMPLE S06 critical benchmark has been calculated using a direct modeling and a two-step modeling approaches. A direct modeling is performed with MCNP6, SERPENT2, CASM04E, and TRITON/NEWT. A two-step modeling is performed by using the nodal code PARCS3.0 employing the homogenized two-group cross section which are generated through SERPENT2, CASM04E and TRITON/NEWT. Detailed calculation models are developed in this paper and the parameters for a two-step modeling generated by each code are compared to each other. Finally, the eigenvalue for DIMPLE S06 are compared to each a direct and a two-step modeling. In this paper, the calculation result of two-step modeling agrees well with that of direct modeling. The result shows that the use of the assembly discontinuity factor in two-step calculation is essential to improve the relative error to the result of a direct modeling. A necessity of the assembly discontinuity factor is clearly proved by calculating the flux distribution for the homogenized assembly.
Publisher
5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015
ISBN
978-151080803-4

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