Calculations and Measurements of Pressure Vessel Thermal Neutron Fluxes in the VVER-1000 Mock-Up in the LR-0 Research Reactor
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F15%3A%230001120" target="_blank" >RIV/26722445:_____/15:#0001120 - isvavai.cz</a>
Výsledek na webu
<a href="http://dx.doi.org/10.1115/1.4029284" target="_blank" >http://dx.doi.org/10.1115/1.4029284</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1115/1.4029284" target="_blank" >10.1115/1.4029284</a>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Calculations and Measurements of Pressure Vessel Thermal Neutron Fluxes in the VVER-1000 Mock-Up in the LR-0 Research Reactor
Popis výsledku v původním jazyce
This paper deals with measured as well as calculated parameters of thermal neutron transport in the reactor pressure vessel model, located behind the LR-0 reactor vessel. A VVER-1000 mock-up core placed in the LR-0 reactor is the source of neutrons, whose transport through heavy steel structures surrounding the core (i.e., the side reflector up to the area behind LR-0 vessel), is studied. The change of neutron distribution due to the variable thickness of the steel reactor pressure vessel (RPV) layers was measured and calculated using MCNPX code. The experimental results are compared with calculations performed with CENDL 3.1 and ENDF/B VII using both the thermal scattering law sublibrary with the S(?,?)S(?,?) model and the free gas transport model. When steel thickness increases, the measured reaction rate attenuation coefficients show a considerable decrease in thermal neutron flux, while measured Cd ratios show a faster decrease in the thermal part of the neutron spectra than the ep
Název v anglickém jazyce
Calculations and Measurements of Pressure Vessel Thermal Neutron Fluxes in the VVER-1000 Mock-Up in the LR-0 Research Reactor
Popis výsledku anglicky
This paper deals with measured as well as calculated parameters of thermal neutron transport in the reactor pressure vessel model, located behind the LR-0 reactor vessel. A VVER-1000 mock-up core placed in the LR-0 reactor is the source of neutrons, whose transport through heavy steel structures surrounding the core (i.e., the side reflector up to the area behind LR-0 vessel), is studied. The change of neutron distribution due to the variable thickness of the steel reactor pressure vessel (RPV) layers was measured and calculated using MCNPX code. The experimental results are compared with calculations performed with CENDL 3.1 and ENDF/B VII using both the thermal scattering law sublibrary with the S(?,?)S(?,?) model and the free gas transport model. When steel thickness increases, the measured reaction rate attenuation coefficients show a considerable decrease in thermal neutron flux, while measured Cd ratios show a faster decrease in the thermal part of the neutron spectra than the ep
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
<a href="/cs/project/ED2.1.00%2F03.0108" target="_blank" >ED2.1.00/03.0108: Udržitelná energetika</a><br>
Návaznosti
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Ostatní
Rok uplatnění
2015
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 Nuclear Engineering and Radiation Science
ISSN
2332-8983
e-ISSN
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Svazek periodika
1
Číslo periodika v rámci svazku
2
Stát vydavatele periodika
US - Spojené státy americké
Počet stran výsledku
7
Strana od-do
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Kód UT WoS článku
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EID výsledku v databázi Scopus
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