Reactor whole core transport calculations without fuel assembly homogenization

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The variational nodal method is generalized by dividing each spatial node into a number of triangular finite elements designated as subelements. The finite subelement trail functions allow for explicit geometry representations within each node, thus eliminating the need for nodal homogenization. The method is implemented within the Argonne National Laboratory code VARIANT and applied to two-dimensional multigroup problems. Eigenvalue and pin-power results are presented for a four-assembly OECD/NEA benchmark problem containing enriched U{sub 2} and MOX fuel pins. Our seven-group model combines spherical or simplified spherical harmonic approximations in angle with isoparametric linear or quadratic subelement basis functions, thus eliminating ... continued below

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Tsoulfanidis, Nicholas; Lewis, Elmer; Smith, M.A.; Palmiotti, G. & Taiwo, T.A. October 18, 2002.

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The variational nodal method is generalized by dividing each spatial node into a number of triangular finite elements designated as subelements. The finite subelement trail functions allow for explicit geometry representations within each node, thus eliminating the need for nodal homogenization. The method is implemented within the Argonne National Laboratory code VARIANT and applied to two-dimensional multigroup problems. Eigenvalue and pin-power results are presented for a four-assembly OECD/NEA benchmark problem containing enriched U{sub 2} and MOX fuel pins. Our seven-group model combines spherical or simplified spherical harmonic approximations in angle with isoparametric linear or quadratic subelement basis functions, thus eliminating the need for fuel-coolant homogenization. Comparisons with reference seven-group Monte Carlo solutions indicate that in the absence of pin-cell homogenization, high-order angular approximations are required to obtain accurate eigenvalues, while the results are substantially less sensitive to the refinement of the finite subelement grids.

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INIS; OSTI as DE00804739

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  • Other Information: PBD: 18 Oct 2002

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  • Report No.: DOE/ID/13632
  • Grant Number: FG07-98ID13632
  • DOI: 10.2172/804739 | External Link
  • Office of Scientific & Technical Information Report Number: 804739
  • Archival Resource Key: ark:/67531/metadc739855

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  • October 18, 2002

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  • Oct. 18, 2015, 6:40 p.m.

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  • Jan. 3, 2017, 1:11 p.m.

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Tsoulfanidis, Nicholas; Lewis, Elmer; Smith, M.A.; Palmiotti, G. & Taiwo, T.A. Reactor whole core transport calculations without fuel assembly homogenization, report, October 18, 2002; United States. (digital.library.unt.edu/ark:/67531/metadc739855/: accessed August 21, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.