A Neutronics Methodology for the NIST Research Reactor Based on MCNXP

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A methodology for calculating inventories for the NBSR has been developed using the MCNPX computer code with the BURN option. A major advantage of the present methodology over the previous methodology, where MONTEBURNS and MCNP5 were used, is that more materials can be included in the model. The NBSR has 30 fuel elements each with a 17.8 cm (7 in) gap in the middle of the fuel. In the startup position, the shim control arms are partially inserted in the top half of the core. During the 38.5 day cycle, the shim arms are slowly removed to their withdrawn (horizontal) ... continued below

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Hanson, A. & Diamond, D. May 16, 2011.

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A methodology for calculating inventories for the NBSR has been developed using the MCNPX computer code with the BURN option. A major advantage of the present methodology over the previous methodology, where MONTEBURNS and MCNP5 were used, is that more materials can be included in the model. The NBSR has 30 fuel elements each with a 17.8 cm (7 in) gap in the middle of the fuel. In the startup position, the shim control arms are partially inserted in the top half of the core. During the 38.5 day cycle, the shim arms are slowly removed to their withdrawn (horizontal) positions. This movement of shim arms causes asymmetries between the burnup of the fuel in the upper and lower halves and across the line of symmetry for the fuel loading. With the MONTEBURNS analyses there was a limitation to the number of materials that could be analyzed so 15 materials in the top half of the core and 15 materials in the bottom half of the core were used, and a half-core (east-west) symmetry was assumed. Since MCNPX allows more materials, this east-west symmetry was not necessary and the core was represented with 60 different materials. The methodology for developing the inventories is presented along with comparisons of neutronic parameters calculated with the previous and present sets of inventories.

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  • 19th International Conference on Nuclear Engineering (ICONE19); Chiba, Japan; 20110516 through 20110519

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  • Report No.: BNL--95208-2011-CP
  • Grant Number: DE-AC02-98CH10886
  • Office of Scientific & Technical Information Report Number: 1020948
  • Archival Resource Key: ark:/67531/metadc836967

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Office of Scientific & Technical Information Technical Reports

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  • May 16, 2011

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  • May 19, 2016, 3:16 p.m.

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  • July 21, 2016, 8:03 p.m.

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Hanson, A. & Diamond, D. A Neutronics Methodology for the NIST Research Reactor Based on MCNXP, article, May 16, 2011; United States. (digital.library.unt.edu/ark:/67531/metadc836967/: accessed November 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.