Determining the axial power profile of partly flooded fuel in a compact core assembled in reactor LR-0

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F16%3AN0000007" target="_blank" >RIV/26722445:_____/16:N0000007 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1016/j.anucene.2015.12.028" target="_blank" >http://dx.doi.org/10.1016/j.anucene.2015.12.028</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.anucene.2015.12.028" target="_blank" >10.1016/j.anucene.2015.12.028</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Determining the axial power profile of partly flooded fuel in a compact core assembled in reactor LR-0

Popis výsledku v původním jazyce

Measurement and calculation of the axial power profile near the boundary of a moderated and non moderated core is used to analyze the suitability of the neutron-physical process description, mainly the angular cross-section of a water-moderated uranium system. This is also an important issue because it affects the radiation situation above the partly flooded core of a water-moderated reactor. Axial power profiles of various fuel pins irradiated on reactor LR-0 were measured and the results were compared with MCNP6 code calculations using the ENDF/B-VILO nuclear data library. The calculated power profile in positions above the moderator level significantly underestimates experimental results. This might be caused by an improper description of the angular distribution of scattered neutrons in a water moderated uranium system.

Název v anglickém jazyce

Determining the axial power profile of partly flooded fuel in a compact core assembled in reactor LR-0

Popis výsledku anglicky

Measurement and calculation of the axial power profile near the boundary of a moderated and non moderated core is used to analyze the suitability of the neutron-physical process description, mainly the angular cross-section of a water-moderated uranium system. This is also an important issue because it affects the radiation situation above the partly flooded core of a water-moderated reactor. Axial power profiles of various fuel pins irradiated on reactor LR-0 were measured and the results were compared with MCNP6 code calculations using the ENDF/B-VILO nuclear data library. The calculated power profile in positions above the moderator level significantly underestimates experimental results. This might be caused by an improper description of the angular distribution of scattered neutrons in a water moderated uranium system.

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

90

Číslo periodika v rámci svazku

April

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

9

Strana od-do

450-458

Kód UT WoS článku

000370106200043

EID výsledku v databázi Scopus

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