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<rdf:RDF xmlns:rdf="http://www.w3.org/1999/02/22-rdf-syntax-ns#" xmlns:dc="http://purl.org/dc/elements/1.1/"><rdf:Description rdf:about="https://repozitorij.uni-lj.si/IzpisGradiva.php?id=164592"><dc:title>Generation and validation of a new WIMS-D library based on ENDF/B-VIII.0</dc:title><dc:creator>Malec,	Jan	(Avtor)
	</dc:creator><dc:creator>Cabellos,	Oscar 	(Avtor)
	</dc:creator><dc:creator>Kromar,	Marjan	(Avtor)
	</dc:creator><dc:creator>Trkov,	Andrej	(Avtor)
	</dc:creator><dc:subject>deterministic transport</dc:subject><dc:subject>depletion calculations</dc:subject><dc:subject>nuclear data</dc:subject><dc:subject>WIMS-D library</dc:subject><dc:description>The WIMSD-5B transport code is a deterministic tool for nuclear reactor core design and fuel management. It can efficiently handle pin-cell and supercell models and calculate homogenized cross sections, which are essential for reactor physics calculations. It is used by core design packages such as the CORD-2 package, developed at the Jožef Stefan Institute, and SEANAP developed by Universidad Politécnica de Madrid (UPM). The WLUP update project https://www-nds.iaea.org/wimsd demonstrated the way to update the WIMS-D libraries with different evaluated nuclear data libraries, including ENDF libraries up to version ENDF/B-VII.1. Using an updated version of the procedure, a new WIMS-D library based on the ENDF/B-VIII.0 data was developed to improve the accuracy of core design calculations. Several improvements to the library were made and the effects of each individual improvement was demonstrated using a 3×3 supercell benchmark model that is representative of a typical pressurized water reactor. Finally, the performance of the library over a diverse set of neutron transport problems was tested for, to ensure no regressions were introduced.</dc:description><dc:date>2025</dc:date><dc:date>2024-11-04 15:02:45</dc:date><dc:type>Članek v reviji</dc:type><dc:identifier>164592</dc:identifier><dc:language>sl</dc:language></rdf:Description></rdf:RDF>
