Lessons learned from applying VIM to fast reactor critical experiments, summary

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VIM is a continuous energy Monte Carlo code first developed around 1970 for the analysis of plate-type, fast-neutron, zero-power critical assemblies. In most respects, VIM is functionally equivalent to the MCNP code but it has two features that make uniquely suited to the analysis of fast reactor critical experiments: (1) the place lattice geometry option, which allows efficient description of and neutron tracking in the assembly geometry, and (2) a statistical treatment of neutron cross section data in the unresolved resonance range. Since its inception, VIM`s capabilities have expanded to include numerous features, such as thermal neutron cross sections, photon ... continued below

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8 p.

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Schaefer, R.W.; McKnight, R.D. & Collins, P.J. May 17, 1995.

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Description

VIM is a continuous energy Monte Carlo code first developed around 1970 for the analysis of plate-type, fast-neutron, zero-power critical assemblies. In most respects, VIM is functionally equivalent to the MCNP code but it has two features that make uniquely suited to the analysis of fast reactor critical experiments: (1) the place lattice geometry option, which allows efficient description of and neutron tracking in the assembly geometry, and (2) a statistical treatment of neutron cross section data in the unresolved resonance range. Since its inception, VIM`s capabilities have expanded to include numerous features, such as thermal neutron cross sections, photon cross sections, and combinatorial and other geometry options, that have allowed its use in a wide range of neutral-particle transport problems. The earliest validation work at Argonne National Laboratory (ANL) focused on the validation of VIM itself. This work showed that, in order for VIM to be a ``rigomus`` tool, extreme detail in the pointwise Monte Carlo libraries was needed, and the required detail was added. The emphasis soon shifted to validating models, methods, data and codes against VIM. Most of this work was done in the context of analyzing critical experiments in zero power reactor (ZPR) assemblies. The purpose of this paper is to present some of the lessons learned from using VIM in ZPR analysis work.

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8 p.

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INIS; OSTI as DE95013400

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  • Nuclear criticality technology and safety project (NCTSP) annual meeting, San Diego, CA (United States), 17 May 1995

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  • Other: DE95013400
  • Report No.: ANL/IFR/SUMM--85772
  • Report No.: CONF-9505195--6-Summ.
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 94673
  • Archival Resource Key: ark:/67531/metadc794809

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

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  • May 17, 1995

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  • Dec. 19, 2015, 7:14 p.m.

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  • Jan. 6, 2016, 2:20 p.m.

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Schaefer, R.W.; McKnight, R.D. & Collins, P.J. Lessons learned from applying VIM to fast reactor critical experiments, summary, article, May 17, 1995; Illinois. (digital.library.unt.edu/ark:/67531/metadc794809/: accessed April 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.