Abstract
Version VI of the ENDF/B nuclear data library was used to develop a set of numerical benchmarks for the Doppler coefficient of reactivity. This was done by using the continuous-energy Monte Carlo code MCNP to calculate eigenvalues of some selected idealized pressurized water reactor pin cell configurations with five different fuel enrichments. Two fuel temperatures corresponding to the hot zero power and the hot full power conditions were considered. These benchmarks are provided for evaluation of the accuracy of light water reactor codes for calculating the system eigenvalue as well as the Doppler coefficient of reactivity. It was found that ENDF/B-VI estimated Doppler coefficients are statistically the same as those based on version V of the nuclear data library.
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