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Continuous Energy Monte Carlo Calculations of Randomly Distributed Spherical Fuels in High-Temperature Gas-Cooled Reactors Based on a Statistical Geometry Model

Isao Murata, Takamasa Mori, Masayuki Nakagawa

Nuclear Science and Engineering / Volume 123 / Number 1 / May 1996 / Pages 96-109

Technical Paper / dx.doi.org/10.13182/NSE96-A24215

The method to treat randomly distributed spherical fuels in continuous energy Monte Carlo calculations has been established. In this method, the location of a spherical fuel is sampled probabilistically along the particle flight path from the spatial probability distribution of spherical fuels, called the nearest neighbor distribution. The necessary probability distribution was evaluated by a newly developed Monte Carlo hard sphere packing simulation code, which employs a random vector synthesis method to reduce overlaps of spherical fuels. The obtained probability distribution was validated by comparing a cross-section photograph of a real fuel compact and an X-ray diffraction experimental result. This method was installed in a Monte Carlo particle transport code and validated by an inventory check of spherical fuels and criticality calculations of ordered packing models. Also, an analysis of a critical assembly experiment was performed with the new code. As a result, it was confirmed that the method was applicable to practical reactor analysis. The method established is quite unique in the respect of probabilistically modeling the geometry of a great number of spherical fuels distributed randomly without any loss of the advantage of the continuous energy method.