MONTE CARLO PERTURBATION ANALYSIS OF DIMENSION AND DENSITY VARIATIONS OF THE ANNULAR CORE RESEARCH REACTOR MODEL FUEL
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Jump to search filtersMonte Carlo Perturbation Analysis of Dimension and Density Variations of the Monte Carlo N-Particle Annular Core Research Reactor Model fuel
Abstract not provided.
Random Variation of ACRR Core Report
The research presented in this paper is to be a contribution to a larger research project. The project was designed to test the safety standards of Sandia National Laboratories' ACRR. The MCNP model of the ACRR core is being used to simulate the environment. To test the safety standards, the dimensions and density of the fuel in the core were varied randomly. Each rod had its own dimension and density assigned to it randomly. Ten different cases of the ACRR core were randomly created. The different cases were studied using 640-group neutron fluxes. The fluxes were compared to see how the variations affected the system.
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