The effect of local power increase on neutron flux in internal parts of the VVER-1000 Mock-Up in LR-0 reactor

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000027" target="_blank" >RIV/26722445:_____/18:N0000027 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/60162694:G43__/18:00536175 RIV/00216224:14330/18:00103750

Výsledek na webu

<a href="http://dx.doi.org/10.1016/j.anucene.2018.08.007" target="_blank" >http://dx.doi.org/10.1016/j.anucene.2018.08.007</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.anucene.2018.08.007" target="_blank" >10.1016/j.anucene.2018.08.007</a>

Jazyk výsledku

angličtina

Název v původním jazyce

The effect of local power increase on neutron flux in internal parts of the VVER-1000 Mock-Up in LR-0 reactor

Popis výsledku v původním jazyce

The neutron flux distribution in the internal parts of a reactor is an important parameter which affects the absorbed dose, temperature, and gas production in the materials. Therefore, the knowledge of neutron flux distribution, for example in the baffle, is important for estimation of the radiation-induced swelling and activation of this internal component. The power distribution in the periphery fuel assemblies, mostly the lateral 2-3 pin rows, has considerable influence on neutron and gamma flux in the internal reactor elements. The power distribution in the core is mostly calculated by the reactor operator using diffusion codes. These data are used as an input for transport calculations, e.g., with Monte Carlo for the fluences, displacements per atoms, gamma heating and other important values for radiation damage estimation. This paper aims to compare the experimental and calculated reaction rate distribution in a mock-up of VVER-1000 (VVER-1000 Mock-Up) internals placed in the LR-0 reactor and compares these quantities in case of a partial change of enrichment in one fuel assembly adjacent to the baffle simulator.

Název v anglickém jazyce

The effect of local power increase on neutron flux in internal parts of the VVER-1000 Mock-Up in LR-0 reactor

Popis výsledku anglicky

The neutron flux distribution in the internal parts of a reactor is an important parameter which affects the absorbed dose, temperature, and gas production in the materials. Therefore, the knowledge of neutron flux distribution, for example in the baffle, is important for estimation of the radiation-induced swelling and activation of this internal component. The power distribution in the periphery fuel assemblies, mostly the lateral 2-3 pin rows, has considerable influence on neutron and gamma flux in the internal reactor elements. The power distribution in the core is mostly calculated by the reactor operator using diffusion codes. These data are used as an input for transport calculations, e.g., with Monte Carlo for the fluences, displacements per atoms, gamma heating and other important values for radiation damage estimation. This paper aims to compare the experimental and calculated reaction rate distribution in a mock-up of VVER-1000 (VVER-1000 Mock-Up) internals placed in the LR-0 reactor and compares these quantities in case of a partial change of enrichment in one fuel assembly adjacent to the baffle simulator.

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)

Rok uplatnění

2018

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

—

Svazek periodika

121

Číslo periodika v rámci svazku

November

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

10

Strana od-do

567-576

Kód UT WoS článku

000444668200054

EID výsledku v databázi Scopus

2-s2.0-85051408685