作者: Alfred L. B. Ho , Alexander Sesonske
DOI: 10.13182/NT82-A32978
关键词:
摘要: A fast, yet accurate, fuel cycle analysis methodology was developed to optimize the various options for in-core nuclear management. The encompasses two major parts, a multicycle point reactor model, PUFLAC, and reload pattern optimization code called DSPWR. PUFLAC model provides convenient reliable survey ability explore scheme possibilities while DSPWR utilizes direct search minimize core power peaking with consideration given local power-peaking factor variation. two-dimensional nodal used in this distribution calculations is based on widely code, EPRI-NODE-P, very good agreement obtained. This has been demonstrated by considering an extended burnup three-to-four batch transition using Zion Unit 1 as reference pressurized water plant realistic constraints. four-batch can yield increase uranium utilization of about 5% decrease costs 7%. from three overall 2.4% 4%. fuel-loading patterns optimized satisfy themore » constraint 2 3% margin at beginning-of-cycle.« less