Measurement of gamma field inside the biological concrete shielding of VVER-1000 Mock-Up at the LR-0 reactor
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F25%3AN0000065" target="_blank" >RIV/26722445:_____/25:N0000065 - isvavai.cz</a>
Nalezeny alternativní kódy
RIV/68407700:21340/25:00380692 RIV/00216224:14330/25:00143689
Výsledek na webu
<a href="https://www.sciencedirect.com/science/article/pii/S0306454924006625" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0306454924006625</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.anucene.2024.110999" target="_blank" >10.1016/j.anucene.2024.110999</a>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Measurement of gamma field inside the biological concrete shielding of VVER-1000 Mock-Up at the LR-0 reactor
Popis výsledku v původním jazyce
The long-term operation of existing nuclear power reactors is a crucial concern due to the complexities and expenses associated with replacing key components, such as the reactor pressure vessel and reactor internals. Gamma radiation, a byproduct of nuclear reactions and radioactive decay, significantly influences the lifetime of these components. This radiation is responsible for various degradation pathways leading to void swelling in steel reactor components and cracking or other radiation damage in concrete structures. A study conducted at a full-scale mock-up of the VVER-1000 reactor at the LR-0 zero-power reactor employed HPGe and stilbene measurements to analyze gamma spectra behind the reactor pressure vessel and within concrete biological shielding. While simulations behind the reactor pressure vessel aligned with measurements, notably, a marked overestimation of stilbene spectrum calculations occurred deep in concrete, suggesting potential inaccuracies in radiation predictions for power plant structures.
Název v anglickém jazyce
Measurement of gamma field inside the biological concrete shielding of VVER-1000 Mock-Up at the LR-0 reactor
Popis výsledku anglicky
The long-term operation of existing nuclear power reactors is a crucial concern due to the complexities and expenses associated with replacing key components, such as the reactor pressure vessel and reactor internals. Gamma radiation, a byproduct of nuclear reactions and radioactive decay, significantly influences the lifetime of these components. This radiation is responsible for various degradation pathways leading to void swelling in steel reactor components and cracking or other radiation damage in concrete structures. A study conducted at a full-scale mock-up of the VVER-1000 reactor at the LR-0 zero-power reactor employed HPGe and stilbene measurements to analyze gamma spectra behind the reactor pressure vessel and within concrete biological shielding. While simulations behind the reactor pressure vessel aligned with measurements, notably, a marked overestimation of stilbene spectrum calculations occurred deep in concrete, suggesting potential inaccuracies in radiation predictions for power plant structures.
Klasifikace
Druh
J<sub>imp</sub> - Článek v periodiku v databázi Web of Science
CEP obor
—
OECD FORD obor
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Návaznosti výsledku
Projekt
—
Návaznosti
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Ostatní
Rok uplatnění
2025
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název periodika
Annals of Nuclear Energy
ISSN
0306-4549
e-ISSN
1873-2100
Svazek periodika
211
Číslo periodika v rámci svazku
February
Stát vydavatele periodika
GB - Spojené království Velké Británie a Severního Irska
Počet stran výsledku
12
Strana od-do
1-12
Kód UT WoS článku
001344297000001
EID výsledku v databázi Scopus
2-s2.0-85207029875