Analysis of the Venus PWR (Pressurized Water Reactor) Engineering Mockup Experiment. Phase 1. Source Distribution.

摘要

The neutron fission source distribution in the core of the VENUS PWR Mockup Experiment is computed and compared to experimental measurements. Of particular concern is the accuracy of the source calculation near the core-baffle interface, which is the important region for contributing to RPV fluence. Results indicate that the calculated neutron source distribution within the VENUS core agrees with the experimentally measured values with an average error of less than 3%. At the important core-baffle interface, the agreement is within 3% error, except at the baffle corner, where the error is about 6%. Better accuracy in the calculations can be obtained by applying a detailed space dependent cross-section weighting procedure to the core-baffle interface region.