Monte Carlo solver for UWB1 fast depletion code

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F15%3A00240663" target="_blank" >RIV/68407700:21220/15:00240663 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/49777513:23220/15:43932139

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Monte Carlo solver for UWB1 fast depletion code

Popis výsledku v původním jazyce

International Conference on Nuclear Engineering, Proceedings, ICONE Volume 2015-January, 2015 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015; Makuhari MesseChiba; Japan; 17 May 2015 through 21 May 2015; Code 118695 Monte Carlo solver for UWB1 fast depletion code (Conference Paper) Lovecký, M.ab , Prehradný, J.ac, Škoda, R.acd a Regional Innovation Centre for Electrical Engineering, University of West Bohemia, Univerzitní 8, Plzeh, Czech Republic b ŠKODA JS A.S., Orlík 266, Plzeh, Czech Republic c Czech Technical University, Faculty of Mechanical Engineering, Technická 4, Prague 6, Czech Republic View additional affiliations View references (7) Abstract Research of advanced types of burnable absorbers (BA) in nuclear fuel requires fast depletion code that would be able to calculate broad range of elements, nuclides or their combination. BAs compensate for the initial excess reactivity and consequently allow longer fuel cycles with higher fuel enrichments. Advanced types of BAs would increase fuel utilization by combining rapidly depleted BA like gadolinium with long-term effect of slowly-depleted BA like europium. State-of-art depletion codes require large amount of computational time, therefore, decision to develop fast depletion code was made. Currently developed UWB1 depletion code comprises of transport and burnup solver, both aiming to fast calculation of nuclear fuel depletion. In order to achieve low computational time, selected equations and data libraries describing fuel behavior was simplified, resulting in balanced accuracy and speed of the code. The paper describes validation calculations of Monte Carlo solver that is used in UWB1 depletion code.

Název v anglickém jazyce

Monte Carlo solver for UWB1 fast depletion code

Popis výsledku anglicky

International Conference on Nuclear Engineering, Proceedings, ICONE Volume 2015-January, 2015 23rd International Conference on Nuclear Engineering: Nuclear Power - Reliable Global Energy, ICONE 2015; Makuhari MesseChiba; Japan; 17 May 2015 through 21 May 2015; Code 118695 Monte Carlo solver for UWB1 fast depletion code (Conference Paper) Lovecký, M.ab , Prehradný, J.ac, Škoda, R.acd a Regional Innovation Centre for Electrical Engineering, University of West Bohemia, Univerzitní 8, Plzeh, Czech Republic b ŠKODA JS A.S., Orlík 266, Plzeh, Czech Republic c Czech Technical University, Faculty of Mechanical Engineering, Technická 4, Prague 6, Czech Republic View additional affiliations View references (7) Abstract Research of advanced types of burnable absorbers (BA) in nuclear fuel requires fast depletion code that would be able to calculate broad range of elements, nuclides or their combination. BAs compensate for the initial excess reactivity and consequently allow longer fuel cycles with higher fuel enrichments. Advanced types of BAs would increase fuel utilization by combining rapidly depleted BA like gadolinium with long-term effect of slowly-depleted BA like europium. State-of-art depletion codes require large amount of computational time, therefore, decision to develop fast depletion code was made. Currently developed UWB1 depletion code comprises of transport and burnup solver, both aiming to fast calculation of nuclear fuel depletion. In order to achieve low computational time, selected equations and data libraries describing fuel behavior was simplified, resulting in balanced accuracy and speed of the code. The paper describes validation calculations of Monte Carlo solver that is used in UWB1 depletion code.

Druh

D - Stať ve sborníku

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

<a href="/cs/project/TE01020455" target="_blank" >TE01020455: Centrum pokročilých jaderných technologií (CANUT)</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2015

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

International Conference on Nuclear Engineering, Proceedings, ICONE

ISBN

978-4-88898-256-6

ISSN

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e-ISSN

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Počet stran výsledku

8

Strana od-do

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Název nakladatele

ASME

Místo vydání

New York

Místo konání akce

Makuhari

Datum konání akce

17. 5. 2015

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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