A 3D stylized half-core CANDU benchmark problem

A 3D stylized half-core Canadian deuterium uranium (CANDU) reactor benchmark problem is presented. The benchmark problem is comprised of a heterogeneous lattice of 37-element natural uranium fuel bundles, heavy water moderated, heavy water cooled, with adjuster rods included as reactivity control de...

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Veröffentlicht in:	Annals of nuclear energy 2011-04, Vol.38 (4), p.876-896
Hauptverfasser:	Pounders, Justin M., Rahnema, Farzad, Serghiuta, Dumitru, Tholammakkil, John
Format:	Artikel
Sprache:	eng
Schlagworte:	Benchmark problem Benchmark results Benchmarking CANDU Heavy water Macroscopic cross section library Monte Carlo methods Monte Carlo results Nuclear power generation Nuclear reactor components Three dimensional Voids Whole core neutron transport
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Beschreibung
Zusammenfassung:	A 3D stylized half-core Canadian deuterium uranium (CANDU) reactor benchmark problem is presented. The benchmark problem is comprised of a heterogeneous lattice of 37-element natural uranium fuel bundles, heavy water moderated, heavy water cooled, with adjuster rods included as reactivity control devices. Furthermore, a 2-group macroscopic cross section library has been developed for the problem to increase the utility of this benchmark for full-core deterministic transport methods development. Monte Carlo results are presented for the benchmark problem in cooled, checkerboard void, and full coolant void configurations.
ISSN:	0306-4549 1873-2100
DOI:	10.1016/j.anucene.2010.10.018