Visualization and analyses of MCNP criticality calculation results

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Careful assessment of the results of a calculation by the code itself can detect mistakes in the problem setup and execution. MCNP has over four hundred error messages that inform the user of FATAL or WARNING errors that have been discovered during processing of just the input file. MCNP4A performs a self assessment of the calculated results to aid the user in determining the quality of the Monte Carlo results. MCNP4A contains new built-in sensitivity analyses of the Monte Carlo calculation that provide the user with simple WARNING messages for both criticality and fixed source calculations. The goal of the ... continued below

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10 p.

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Urbatsch, T.J.; Forster, R.A.; Booth, T.E.; Van Riper, K.A. & Waters, L.S. July 1, 1995.

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Description

Careful assessment of the results of a calculation by the code itself can detect mistakes in the problem setup and execution. MCNP has over four hundred error messages that inform the user of FATAL or WARNING errors that have been discovered during processing of just the input file. MCNP4A performs a self assessment of the calculated results to aid the user in determining the quality of the Monte Carlo results. MCNP4A contains new built-in sensitivity analyses of the Monte Carlo calculation that provide the user with simple WARNING messages for both criticality and fixed source calculations. The goal of the new analyses described in this paper is to provide the MCNP criticality practitioner with enough information in the output to assess the validity of the k{sub eff} calculation and any associated tallies. The results of these checks are presented in the k{sub eff} results summary, several k{sub eff} tables and graphs, and tally tables and graphs. Plots of k{sub eff} at the workstation are also available as the problem is running or in a postprocessing mode to assess problem performance and results. Plots of the fission source by cycle supply valuable visual information, although they are not yet available in the production version of MCNP.

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10 p.

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INIS; OSTI as DE95015283

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  • 5. international conference on nuclear criticality safety, Albuquerque, NM (United States), 17-22 Sep 1995

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  • Other: DE95015283
  • Report No.: LA-UR--95-2058
  • Report No.: CONF-9509100--21
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 102513
  • Archival Resource Key: ark:/67531/metadc621157

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • July 1, 1995

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  • June 16, 2015, 7:43 a.m.

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  • Feb. 29, 2016, 12:43 p.m.

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Urbatsch, T.J.; Forster, R.A.; Booth, T.E.; Van Riper, K.A. & Waters, L.S. Visualization and analyses of MCNP criticality calculation results, article, July 1, 1995; New Mexico. (digital.library.unt.edu/ark:/67531/metadc621157/: accessed July 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.