@inproceedings{8896faf3f24048b49b04eda91bface9b,
title = "The modeling of advanced BWR fuel designs with the U.S. NRC fuel depletion codes PARCS/PATHS",
abstract = "The modeling of advanced BWR fuel designs during fuel depletion requires the explicit treatment of part length fuel rods and a heterogeneous axial flow geometry in the fuel channel. The U.S. NRC fuel depletion codes PARCS/PATHS were modified to model advanced fuel designs and validated using previously benchmarked advanced core simulators as well as BWR plant and experimental data. The modifications to the codes and the results of the validation are described in this paper.",
keywords = "BWR, Depletion, Simulator",
author = "A. Wysocki and J. March-Leuba and C. Thurston and N. Hudson and A. Ireland and A. Ward and A. Manera and Y. Xu and T. Downar",
year = "2014",
language = "English",
series = "Embedded Topical Meeting on Advances in Thermal Hydraulics, ATH 2014, Held at the American Nuclear Society 2014 Annual Meeting",
publisher = "American Nuclear Society",
pages = "136--147",
booktitle = "Embedded Topical Meeting on Advances in Thermal Hydraulics, ATH 2014, Held at the American Nuclear Society 2014 Annual Meeting",
note = "Embedded Topical Meeting on Advances in Thermal Hydraulics, ATH 2014, Held at the American Nuclear Society 2014 Annual Meeting ; Conference date: 15-06-2014 Through 19-06-2014",
}