Title:	Impact of burnable absobers on nuclear data uncertainty analysis for fuel assembly depletion
Authors:	Lovecký, Martin Závorka, Jiří Jiřičková, Jana Škoda, Radek
Citation:	LOVECKÝ, M.., ZÁVORKA, J.., JIŘIČKOVÁ, J.., ŠKODA, R.. Impact of burnable absobers on nuclear data uncertainty analysis for fuel assembly depletion. In: Proceedings : 28th International Conference Nuclear Energy for New Europe (NENE 2019). Ljubljana: Nuclear Society of Slovenia, 2019. s. 606.1-606.8. ISBN 978-961-6207-47-8.
Issue Date:	2019
Publisher:	Nuclear Society of Slovenia
Document type:	konferenční příspěvek conferenceObject
URI:	http://hdl.handle.net/11025/36645
ISBN:	978-961-6207-47-8
Keywords in different language:	burnable absorber;uncertainty;SCALE;nuclear data
Abstract in different language:	Nuclear data uncertainty propagation can be analyzed for various applications. Uncertainty of neutron multiplication factor during fuel depletion is the response quantity of interest for burnable absorber research. Three different fuel assembly (FA) designs were analyzed, FA without burnable absorber (BA), FA with gadolinium bearing rods in selected positions and finally, FA with uniform BA loading in all fuel pins. Newly developed BA materials would be introduced faster into reactor operation if they improve not only neutronics, but other safety or economics-related issues, i.e. accident tolerant fuel. Uniform BA loading is required for technical-economical analyses. VVER-440 fuel assembly depletion with non-uniform gadolinium and uniform erbium BA designs were analyzed with SCALE code package in order to show the effect of BA design on reactivity uncertainty. Nuclear data uncertainty analysis methods can be divided into first order perturbation theory based methods (TSUNAMI in SCALE) and Monte Carlo sampling methods (SAMPLER in SCALE). The first method has the advantage in fast calculation time due to the use of adjoint-based sensitivity approach, on the other hand, it is efficient only for a sufficiently small number of responses. The latter method requires performing large number of costly transport calculations, but can become quite competitive for complex models.
Rights:	Plný text je přístupný v rámci univerzity přihlášeným uživatelům. © Nuclear Society of Slovenia
Appears in Collections:	Konferenční příspěvky / Conference papers (KEE) Konferenční příspěvky / Conference papers (RICE) OBD

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