Study of graphite reactivity worth on well-defined cores assembled on LR-0 reactor

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F16%3AN0000008" target="_blank" >RIV/26722445:_____/16:N0000008 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1016/j.anucene.2015.10.010" target="_blank" >http://dx.doi.org/10.1016/j.anucene.2015.10.010</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.anucene.2015.10.010" target="_blank" >10.1016/j.anucene.2015.10.010</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Study of graphite reactivity worth on well-defined cores assembled on LR-0 reactor

Popis výsledku v původním jazyce

Graphite is an often-used moderating material on the basis of its good moderating power and very low absorption cross section. This small absorption cross section permits the use of natural or low-enriched uranium in graphite moderated reactors. Graphite is now being considered as the moderator for Fluoride-salt-cooled High Temperature Reactors (FHR). The critical moderator level was measured for various graphite block configurations in an experimental dry assembly of the LR-0 reactor. Comparisons with experiments were performed between Monte Carlo simulation tools for which satisfactory agreement was obtained with the exception of some systematic discrepancies. The larger discrepancies were observed when using the ENDF/B-VII.0 library. To decrease the uncertainties, based on conservative assumptions, relative comparisons were done. The results provided by the different nuclear data libraries are within 3 sigma interval of experimental uncertainties. It has been determined that differences between the results of calculations are caused by variations in the (n,n), (n,n'), (n,g) reactions and also by various angular distributions, while the (n,g) cross section variations play only a minor role for these configurations.

Název v anglickém jazyce

Study of graphite reactivity worth on well-defined cores assembled on LR-0 reactor

Popis výsledku anglicky

Graphite is an often-used moderating material on the basis of its good moderating power and very low absorption cross section. This small absorption cross section permits the use of natural or low-enriched uranium in graphite moderated reactors. Graphite is now being considered as the moderator for Fluoride-salt-cooled High Temperature Reactors (FHR). The critical moderator level was measured for various graphite block configurations in an experimental dry assembly of the LR-0 reactor. Comparisons with experiments were performed between Monte Carlo simulation tools for which satisfactory agreement was obtained with the exception of some systematic discrepancies. The larger discrepancies were observed when using the ENDF/B-VII.0 library. To decrease the uncertainties, based on conservative assumptions, relative comparisons were done. The results provided by the different nuclear data libraries are within 3 sigma interval of experimental uncertainties. It has been determined that differences between the results of calculations are caused by variations in the (n,n), (n,n'), (n,g) reactions and also by various angular distributions, while the (n,g) cross section variations play only a minor role for these configurations.

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

CEP obor

JF - Jaderná energetika

OECD FORD obor

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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>Z - Vyzkumny zamer (s odkazem do CEZ)

Rok uplatnění

2016

Kód důvěrnosti údajů

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

Název periodika

Annals of Nuclear Energy

ISSN

0306-4549

e-ISSN

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Svazek periodika

87

Číslo periodika v rámci svazku

January

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

11

Strana od-do

601-611

Kód UT WoS článku

000367697800065

EID výsledku v databázi Scopus

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