Comparison of ENDF/B-VII.1 and JEFF-3.2 in VVER-1000 operational data calculation

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F17%3A00315986" target="_blank" >RIV/68407700:21340/17:00315986 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.epj-conferences.org/articles/epjconf/abs/2017/15/epjconf-nd2016_09024/epjconf-nd2016_09024.html" target="_blank" >https://www.epj-conferences.org/articles/epjconf/abs/2017/15/epjconf-nd2016_09024/epjconf-nd2016_09024.html</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1051/epjconf/201714609024" target="_blank" >10.1051/epjconf/201714609024</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Comparison of ENDF/B-VII.1 and JEFF-3.2 in VVER-1000 operational data calculation

Popis výsledku v původním jazyce

Safe operation of a nuclear reactor requires an extensive calculational support. Operational data are determined by full-core calculations during the design phase of a fuel loading. Loading pattern and design of fuel assemblies are adjusted to meet safety requirements and optimize reactor operation. Nodal diffusion code ANDREA is used for this task in case of Czech VVER-1000 reactors. Nuclear data for this diffusion code are prepared regularly by lattice code HELIOS. These calculations are conducted in 2D on fuel assembly level. There is also possibility to calculate these macroscopic data by Monte-Carlo Serpent code. It can make use of alternative evaluated libraries. All calculations are affected by inherent uncertainties in nuclear data. It is useful to see results of full-core calculations based on two sets of diffusion data obtained by Serpent code calculations with ENDF/B-VII.1 and JEFF-3.2 nuclear data including also decay data library and fission yields data. The comparison is based directly on fuel assembly level macroscopic data and resulting operational data. This study illustrates effect of evaluated nuclear data library on full-core calculations of a large PWR reactor core. The level of difference which results exclusively from nuclear data selection can help to understand the level of inherent uncertainties of such full-core calculations.

Název v anglickém jazyce

Comparison of ENDF/B-VII.1 and JEFF-3.2 in VVER-1000 operational data calculation

Popis výsledku anglicky

Safe operation of a nuclear reactor requires an extensive calculational support. Operational data are determined by full-core calculations during the design phase of a fuel loading. Loading pattern and design of fuel assemblies are adjusted to meet safety requirements and optimize reactor operation. Nodal diffusion code ANDREA is used for this task in case of Czech VVER-1000 reactors. Nuclear data for this diffusion code are prepared regularly by lattice code HELIOS. These calculations are conducted in 2D on fuel assembly level. There is also possibility to calculate these macroscopic data by Monte-Carlo Serpent code. It can make use of alternative evaluated libraries. All calculations are affected by inherent uncertainties in nuclear data. It is useful to see results of full-core calculations based on two sets of diffusion data obtained by Serpent code calculations with ENDF/B-VII.1 and JEFF-3.2 nuclear data including also decay data library and fission yields data. The comparison is based directly on fuel assembly level macroscopic data and resulting operational data. This study illustrates effect of evaluated nuclear data library on full-core calculations of a large PWR reactor core. The level of difference which results exclusively from nuclear data selection can help to understand the level of inherent uncertainties of such full-core calculations.

Druh

D - Stať ve sborníku

CEP obor

—

OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

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

Rok uplatnění

2017

Kód důvěrnosti údajů

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

Název statě ve sborníku

ND 2016: International Conference on Nuclear Data for Science and Technology

ISBN

978-2-7598-9020-0

ISSN

2100-014X

e-ISSN

2100-014X

Počet stran výsledku

4

Strana od-do

—

Název nakladatele

EDP Sciences - Web of Conferences

Místo vydání

Les Ulis Cedex A

Místo konání akce

Bruges

Datum konání akce

11. 9. 2016

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

000426429500251