Examination of pin-by-pin fission rate distribution in large geometry evaluated by the Monte-Carlo method

Accuracy and reliability of pin-by-pin fission rate distribution in large geometries calculated by the multi-group Monte-Carlo method is examined through comparison with a deterministic transport code based on the method of characteristics. Various calculation geometries from a single assembly to a PWR full core are used for comparison of pin-by-pin fission rate distribution. An integral parameter, i.e., k-effective, can be accurately calculated by the Monte-Carlo method with a practical number of neutron histories (106-107) regardless of the size of the calculation geometry. On the other hand, comparison with the deterministic calculation shows that the estimated statistical errors for pin-by-pin fission rate distribution obtained by a Monte-Carlo calculation are somewhat underestimated in a large geometry, e.g., a PWR full core, under the present calculation conditions. Such underestimation of the statistical uncertainty of a local parameter should be carefully considered when the Monte-Carlo method is used as a reference tool for verification of a deterministic code, especially in large geometries.