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논문 기본 정보

자료유형
학술저널
저자정보
Petra Mala (Ecole Polytechnique Federale de Lausanne Switzerland) Andreas Pautz (Ecole Polytechnique Federale de Lausanne Switzerland)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제11호
발행연도
2020.11
수록면
2,431 - 2,441 (11page)
DOI
https://doi.org/10.1016/j.net.2020.04.022

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Currently, the pin-by-pin homogenized solvers are a very active research field as they can, unlike thenodal codes, directly predict the local power, while requiring significantly less computational resourcesthan the heterogeneous transport codes. This paper presents a recently developed pin-by-pin diffusion/SP3 solver Tortin, its spatial discretization method and the reflector treatment. Regarding the spatialdiscretization, it was observed that the finite difference method applied on pin-cell size mesh does notproperly capture the big flux change between MOX and uranium fuel, while the nodal expansion methodis more accurate but too slow. If the finite difference method is used with a finer mesh in the outer twopin rows of the fuel assembly, it increases the required computation time by only 50%, but decreases thepin power errors below 1% with respect to lattice code reference solutions. The paper further describesthe coupling of Tortin with a microscopic depletion solver. Several verification tests show that the SP3pin-by-pin solver can reproduce the heterogeneous transport solvers results with very good accuracy,even for fuel cycle depletion of very heterogeneous core employing MOX fuel or inserted control rods,while being two orders of magnitude faste

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