Neutron flux measurement and calculation behind VVER-1000 reactor pressure vessel simulator placed in LR-0 reactor

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F15%3A%230001128" target="_blank" >RIV/26722445:_____/15:#0001128 - isvavai.cz</a>

Výsledek na webu

—

DOI - Digital Object Identifier

—

Jazyk výsledku

angličtina

Název v původním jazyce

Neutron flux measurement and calculation behind VVER-1000 reactor pressure vessel simulator placed in LR-0 reactor

Popis výsledku v původním jazyce

The neutron fluence in the reactor pressure vessel is an important physical quantity affecting material degradation, which reflects in the vessel residual lifetime. The measured fluxes are normalized per 1nA of monitor current, which corresponds to 0.01W of thermal power, or 3.631E8 fiss/s. The scaling factor for such evaluation was determined from neutron flux in reference position, evaluated by means of reaction rate in well defined activation detector. This scaling factor was verified by means of gamma spectroscopy of irradiated fuel. This independent method is based on the proportionality between the net peak area (NPA) of selected fission product and released energy. 92Sr fission product is used on the LR-0 reactor due to its suitable values of gamma energies with no parasitic peaks and half-life allowing reasonable manipulation time after irradiation. 92Sr has also no coincidence photons with measurable activity after defined irradiation conditions and it has also little differe

Název v anglickém jazyce

Neutron flux measurement and calculation behind VVER-1000 reactor pressure vessel simulator placed in LR-0 reactor

Popis výsledku anglicky

The neutron fluence in the reactor pressure vessel is an important physical quantity affecting material degradation, which reflects in the vessel residual lifetime. The measured fluxes are normalized per 1nA of monitor current, which corresponds to 0.01W of thermal power, or 3.631E8 fiss/s. The scaling factor for such evaluation was determined from neutron flux in reference position, evaluated by means of reaction rate in well defined activation detector. This scaling factor was verified by means of gamma spectroscopy of irradiated fuel. This independent method is based on the proportionality between the net peak area (NPA) of selected fission product and released energy. 92Sr fission product is used on the LR-0 reactor due to its suitable values of gamma energies with no parasitic peaks and half-life allowing reasonable manipulation time after irradiation. 92Sr has also no coincidence photons with measurable activity after defined irradiation conditions and it has also little differe

Druh

O - Ostatní výsledky

CEP obor

JF - Jaderná energetika

OECD FORD obor

—

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)<br>Z - Vyzkumny zamer (s odkazem do CEZ)

Rok uplatnění

2015

Kód důvěrnosti údajů

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