The use of WIMS-ANL lumped fission product cross sections for burned core analysis with the MCNP Monte Carlo code.

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Description

Most Monte Carlo neutronics analyses are performed for fresh cores. To model snapshots of the cores at different stages during burnup using MCNP, a method is presented that uses lumped fission product (LFP) cross sections generated by the WIMS-ANL code and processed for use in MCNP. Results of analyses for four very different reactor cores using MTR-type and Russian-designed fuel assemblies, with LEU and HEU fuels, are provided to demonstrate the use of this method.

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9 p.

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Hanan, N. A. October 14, 1998.

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 18 times . More information about this article can be viewed below.

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Description

Most Monte Carlo neutronics analyses are performed for fresh cores. To model snapshots of the cores at different stages during burnup using MCNP, a method is presented that uses lumped fission product (LFP) cross sections generated by the WIMS-ANL code and processed for use in MCNP. Results of analyses for four very different reactor cores using MTR-type and Russian-designed fuel assemblies, with LEU and HEU fuels, are provided to demonstrate the use of this method.

Physical Description

9 p.

Notes

INIS; OSTI as DE00011044

Medium: P; Size: 9 pages

Source

  • 21st International Meeting on Reduced Enrichment for Research and Test Reactors, Sao Paulo (BR), 10/18/1998--10/23/1998

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  • Report No.: ANL/TD/CP-97460
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 11044
  • Archival Resource Key: ark:/67531/metadc623046

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  • October 14, 1998

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • April 11, 2017, 8:10 p.m.

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Hanan, N. A. The use of WIMS-ANL lumped fission product cross sections for burned core analysis with the MCNP Monte Carlo code., article, October 14, 1998; Illinois. (digital.library.unt.edu/ark:/67531/metadc623046/: accessed September 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.