Analysis of Moderator Temperature Coefficient With Neutron Spectrum for Pressurized Water Reactor
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Graphical Abstract
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Abstract
In pressurized water reactor, the H2O/U ratio and 235U enrichment are important parameters affecting the distribution of neutron spectrum. The variation of two-group neutron spectra with burnup was analyzed under the different H2O/U ratios and 235U enrichments. The moderator temperature coefficient was analyzed by using neutron spectrum. The results show that the core has a minimum moderator temperature coefficient with H2O/U ratio change at given 235U enrichment condition, and the increase of 235U enrichment and burnup may not lead to more negative for moderator temperature coefficient.
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