Reflector macroscopic cross-section data uncertainties effect on the nodal code full-core calculation

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F20%3A00342305" target="_blank" >RIV/68407700:21340/20:00342305 - isvavai.cz</a>

Výsledek na webu

<a href="https://doi.org/10.1016/j.nucengdes.2020.110743" target="_blank" >https://doi.org/10.1016/j.nucengdes.2020.110743</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.nucengdes.2020.110743" target="_blank" >10.1016/j.nucengdes.2020.110743</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Reflector macroscopic cross-section data uncertainties effect on the nodal code full-core calculation

Popis výsledku v původním jazyce

The nodal codes still represent the key computational part of the nuclear power plant operation analysis. The mathematical model in the codes is connected with physical interpretation via macroscopic cross-section libraries. These data are generated using lattice codes, where the exact geometry is simulated. The uncertainties of the microscopic cross-sections and other geometrical uncertainties are typically not transferred from the lattice codes into the macroscopic libraries. This analysis starts with existing macroscopic data for radial reactor core reflectors and anticipated uncertainties of these data and investigates sensitivity of the critical boron concentration as well as the power prediction in the core to variations of these data. The provided analysis showed strong stability of the results with the changing reflector cross-section characteristics. Even with the highest perturbations of the reflector data the critical boron concentration was not changed by more than 0.15 % and pin power was predicted with less than 1.65% difference. The effects were found to be largely localized.

Název v anglickém jazyce

Reflector macroscopic cross-section data uncertainties effect on the nodal code full-core calculation

Popis výsledku anglicky

The nodal codes still represent the key computational part of the nuclear power plant operation analysis. The mathematical model in the codes is connected with physical interpretation via macroscopic cross-section libraries. These data are generated using lattice codes, where the exact geometry is simulated. The uncertainties of the microscopic cross-sections and other geometrical uncertainties are typically not transferred from the lattice codes into the macroscopic libraries. This analysis starts with existing macroscopic data for radial reactor core reflectors and anticipated uncertainties of these data and investigates sensitivity of the critical boron concentration as well as the power prediction in the core to variations of these data. The provided analysis showed strong stability of the results with the changing reflector cross-section characteristics. Even with the highest perturbations of the reflector data the critical boron concentration was not changed by more than 0.15 % and pin power was predicted with less than 1.65% difference. The effects were found to be largely localized.

Druh

J_imp - Článek v periodiku v databázi Web of Science

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)<br>S - Specificky vyzkum na vysokych skolach

Rok uplatnění

2020

Kód důvěrnosti údajů

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

Název periodika

Nuclear Engineering and Design

ISSN

0029-5493

e-ISSN

1872-759X

Svazek periodika

366

Číslo periodika v rámci svazku

110743

Stát vydavatele periodika

NL - Nizozemsko

Počet stran výsledku

9

Strana od-do

—

Kód UT WoS článku

000558754700001

EID výsledku v databázi Scopus

2-s2.0-85088399587