Calculation and measurement of neutron flux in the VVER-1000 mock-up on the LR-0 research reactor

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F12%3A%230000650" target="_blank" >RIV/26722445:_____/12:#0000650 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21340/12:00189948

Výsledek na webu

<a href="http://dx.doi.org/10.1016/j.anucene.2011.10.003" target="_blank" >http://dx.doi.org/10.1016/j.anucene.2011.10.003</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.anucene.2011.10.003" target="_blank" >10.1016/j.anucene.2011.10.003</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Calculation and measurement of neutron flux in the VVER-1000 mock-up on the LR-0 research reactor

Popis výsledku v původním jazyce

The neutron fluence load on a reactor pressure vessel is an important physical quantity affecting material degradation and consequently reliable assessment of pressure vessel integrity and lifetime prolongation beyond designed conditions. This degradation is influenced by mixed neutron-photon source from the core periphery as well as by material parameters of the reactor pressure vessel. Computational procedures and experimental determination of neutron fluxes in the VVER-1000 mock-up internal structures as well as the results achieved are described in this paper. The calculation were performed with the MCNPX code with different nuclear data libraries. Nuclear data were processed using NJOY code. The neutron spectra measurements were performed with a two-parameter stilbene spectrometer.

Název v anglickém jazyce

Calculation and measurement of neutron flux in the VVER-1000 mock-up on the LR-0 research reactor

Popis výsledku anglicky

The neutron fluence load on a reactor pressure vessel is an important physical quantity affecting material degradation and consequently reliable assessment of pressure vessel integrity and lifetime prolongation beyond designed conditions. This degradation is influenced by mixed neutron-photon source from the core periphery as well as by material parameters of the reactor pressure vessel. Computational procedures and experimental determination of neutron fluxes in the VVER-1000 mock-up internal structures as well as the results achieved are described in this paper. The calculation were performed with the MCNPX code with different nuclear data libraries. Nuclear data were processed using NJOY code. The neutron spectra measurements were performed with a two-parameter stilbene spectrometer.

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

<a href="/cs/project/1H-PK2%2F05" target="_blank" >1H-PK2/05: Využití progresivních metod detekce neutronů a fotonů v aplikovaném výzkumu pro potřeby monitorování a hodnocení bezpečnosti a spolehlivosti jaderných zařízení.</a><br>

Návaznosti

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

Rok uplatnění

2012

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

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Svazek periodika

40

Číslo periodika v rámci svazku

1

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

10

Strana od-do

25-34

Kód UT WoS článku

000299918900003

EID výsledku v databázi Scopus

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