Lessons learned from applying VIM to fast reactor critical experiments

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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 plate 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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10 p.

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

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  • Argonne National Laboratory
    Publisher Info: Argonne National Lab., Idaho Falls, ID (United States)
    Place of Publication: Idaho Falls, Idaho

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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 plate 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 ``rigorous`` 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. This involves such areas as uncovering problems in deterministic methods and models, pitfalls in using Monte Carlo codes, and improving predictions. The numerical illustrations included here were taken from the extensive documentation cited as references.

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10 p.

Notes

INIS; OSTI as DE95013549

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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: DE95013549
  • Report No.: ANL/ED/CP--85772
  • Report No.: CONF-9505195--9
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 102529
  • Archival Resource Key: ark:/67531/metadc620450

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  • May 17, 1995

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  • June 16, 2015, 7:43 a.m.

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  • Jan. 6, 2016, 4:54 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, article, May 17, 1995; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc620450/: accessed September 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.