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

Result code in 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>

Result on the web

<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>

Result language

angličtina

Original language name

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

Original language description

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.

Czech name

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Czech description

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Type

D - Article in proceedings

CEP classification

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OECD FORD branch

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

Project

Result was created during the realization of more than one project. More information in the Projects tab.

Continuities

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

Publication year

2017

Confidentiality

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

Article name in the collection

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

ISBN

978-2-7598-9020-0

ISSN

2100-014X

e-ISSN

2100-014X

Number of pages

4

Pages from-to

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Publisher name

EDP Sciences - Web of Conferences

Place of publication

Les Ulis Cedex A

Event location

Bruges

Event date

Sep 11, 2016

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

000426429500251