Comparison of Attenuation Coefficients for VVER-440 and VVER-1000 Pressure Vessels
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F12%3A%230000702" target="_blank" >RIV/26722445:_____/12:#0000702 - isvavai.cz</a>
Výsledek na webu
<a href="http://www.astm.org/DIGITAL_LIBRARY/JOURNALS/JAI/PAGES/JAI104055.htm" target="_blank" >http://www.astm.org/DIGITAL_LIBRARY/JOURNALS/JAI/PAGES/JAI104055.htm</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1520/JAI104055" target="_blank" >10.1520/JAI104055</a>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Comparison of Attenuation Coefficients for VVER-440 and VVER-1000 Pressure Vessels
Popis výsledku v původním jazyce
The paper summarizes the attenuation coefficient of the neutron fluence with E?>?0.5 MeV through a reactor pressure vessel for vodo-vodyanoi energetichesky reactor (VVER) reactor types measured and/or calculated for mock-up experiments, as well as for operated nuclear power plant (NPP) units. The attenuation coefficient is possible to evaluate directly only by using the retro-dosimetry, based on a combination of the measured activities from the weld sample and concurrent ex-vessel measurement. The available neutron fluence attenuation coefficients (E?>?0.5 MeV), calculated and measured at a mock-up experiment simulating the VVER-440-unit conditions, vary from 3.5 to 6.15. A similar situation is used for the calculations and mock-up experiment measurements for the VVER-1000 RPV, where the attenuation coefficient of the neutron fluence varies from 5.99 to 8.85. Because of the difference in calculations for the real units and the mock-up experiments, the necessity to design and perform ca
Název v anglickém jazyce
Comparison of Attenuation Coefficients for VVER-440 and VVER-1000 Pressure Vessels
Popis výsledku anglicky
The paper summarizes the attenuation coefficient of the neutron fluence with E?>?0.5 MeV through a reactor pressure vessel for vodo-vodyanoi energetichesky reactor (VVER) reactor types measured and/or calculated for mock-up experiments, as well as for operated nuclear power plant (NPP) units. The attenuation coefficient is possible to evaluate directly only by using the retro-dosimetry, based on a combination of the measured activities from the weld sample and concurrent ex-vessel measurement. The available neutron fluence attenuation coefficients (E?>?0.5 MeV), calculated and measured at a mock-up experiment simulating the VVER-440-unit conditions, vary from 3.5 to 6.15. A similar situation is used for the calculations and mock-up experiment measurements for the VVER-1000 RPV, where the attenuation coefficient of the neutron fluence varies from 5.99 to 8.85. Because of the difference in calculations for the real units and the mock-up experiments, the necessity to design and perform ca
Klasifikace
Druh
J<sub>x</sub> - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)
CEP obor
JF - Jaderná energetika
OECD FORD obor
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Návaznosti výsledku
Projekt
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Návaznosti
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Ostatní
Rok uplatnění
2012
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název periodika
Journal of ASTM International
ISSN
1546-962X
e-ISSN
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Svazek periodika
9
Číslo periodika v rámci svazku
4
Stát vydavatele periodika
US - Spojené státy americké
Počet stran výsledku
7
Strana od-do
1-7
Kód UT WoS článku
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EID výsledku v databázi Scopus
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