Lessons learned from applying VIM to fast reactor critical experiments, summary
Conference
·
OSTI ID:94673
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.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 94673
- Report Number(s):
- ANL/IFR/SUMM--85772; CONF-9505195--6-Summ.; ON: DE95013400
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
CROSS SECTIONS
GCFR REACTOR
LMFBR TYPE REACTORS
MONTE CARLO METHOD
REACTOR CORES
REACTOR LATTICES
REACTOR PHYSICS
V CODES
ZERO POWER REACTORS
ZPPR REACTOR
ZPR REACTOR
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22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
CROSS SECTIONS
GCFR REACTOR
LMFBR TYPE REACTORS
MONTE CARLO METHOD
REACTOR CORES
REACTOR LATTICES
REACTOR PHYSICS
V CODES
ZERO POWER REACTORS
ZPPR REACTOR
ZPR REACTOR
ZPR-6 REACTOR
ZPR-9 REACTOR