Calculations and Measurements of Pressure Vessel Thermal Neutron Fluxes in the VVER-1000 Mock-Up in the LR-0 Research Reactor

Kód výsledku v IS VaVaI

RIV/26722445:_____/15:#0001120 - isvavai.cz

Výsledek na webu

http://dx.doi.org/10.1115/1.4029284

DOI - Digital Object Identifier

10.1115/1.4029284

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

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

ED2.1.00/03.0108: Udržitelná energetika

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2015

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

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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