ENDF B-VI BENCHMARK CALCULATIONS FOR THE DOPPLER COEFFICIENT OF REACTIVITY/

Version VI of the ENDF/B nuclear data library was used to develop a se t of numerical benchmarks for the Doppler coefficient of reactivity. T his was done by using the continuous-energy Monte Carlo code MCNP to c alculate eigenvalues of some selected idealized pressurized water reac tor 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 e valuation of the accuracy of light water reactor codes for calculating the system eigenvalue as well as the Doppler coefficient of reactivit y. It was found that ENDF/B-VI estimated Doppler coefficients are stat istically the same as those based on version V of the nuclear data lib rary. Copyright (C) 1996 Elsevier Science Ltd