Burnable Absorber Selection With UWB1 Depletion Code

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F14%3A00227184" target="_blank" >RIV/68407700:21220/14:00227184 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/49777513:23220/14:43922387

Výsledek na webu

<a href="http://dx.doi.org/10.1115/ICONE22-30870" target="_blank" >http://dx.doi.org/10.1115/ICONE22-30870</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1115/ICONE22-30870" target="_blank" >10.1115/ICONE22-30870</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Burnable Absorber Selection With UWB1 Depletion Code

Popis výsledku v původním jazyce

Research of nuclear reactor fuel depletion aims at development and introduction of advanced types of burnable absorbers (BA) applied within nuclear fuel. BAs compensate for the initial reactivity excess and consequently may allow for lower power peakingfactors and longer fuel cycles with higher fuel enrichments. Modern computer codes for nuclear fuel depletion calculation require a substantial amount of computational time. Therefore, any parametric calculations for BA selection need to be carried out only with a fast depletion code. The main purpose of the newly developed UWB1 code is a rapid calculation of nuclear fuel depletion, which is achieved by the approximations in the equations describing transport part of fuel depletion. Microscopic cross sections are assumed to be constant through depletion calculation steps. The paper describes the first step of analysis using a new version of UWB1, that was accomplished with the assumption of uniformly distributed BA in fuel. BA elements,

Název v anglickém jazyce

Burnable Absorber Selection With UWB1 Depletion Code

Popis výsledku anglicky

Research of nuclear reactor fuel depletion aims at development and introduction of advanced types of burnable absorbers (BA) applied within nuclear fuel. BAs compensate for the initial reactivity excess and consequently may allow for lower power peakingfactors and longer fuel cycles with higher fuel enrichments. Modern computer codes for nuclear fuel depletion calculation require a substantial amount of computational time. Therefore, any parametric calculations for BA selection need to be carried out only with a fast depletion code. The main purpose of the newly developed UWB1 code is a rapid calculation of nuclear fuel depletion, which is achieved by the approximations in the equations describing transport part of fuel depletion. Microscopic cross sections are assumed to be constant through depletion calculation steps. The paper describes the first step of analysis using a new version of UWB1, that was accomplished with the assumption of uniformly distributed BA in fuel. BA elements,

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

2014

Kód důvěrnosti údajů

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

Název statě ve sborníku

22nd International Conference on Nuclear Engineering

ISBN

978-0-7918-4589-9

ISSN

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e-ISSN

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Počet stran výsledku

10

Strana od-do

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Název nakladatele

ASME

Místo vydání

New York

Místo konání akce

Prague

Datum konání akce

7. 7. 2014

Typ akce podle státní příslušnosti

EUR - Evropská akce

Kód UT WoS článku

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