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

Kód výsledku v IS VaVaI

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Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Neutron flux measurement and calculation behind wer-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 InA of monitor current, which corresponds to 0.01 W 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 difference between the theoretical and measured decay. Both neutron and photon transport calculations were performed with the MCNPX 2.6.0 code with different nuclear data libraries. The fast fluxes behind the reactor pressure vessel (RPV) simulator were calculated using fixed source model with defined (calculated by MCNPX) power density across core. The results clearly show the distinguishable dependency of nuclear data libraries on the results. The effect of different libraries is mostly notable in the fluxes over 5 MeV, where the JENDL 4 results overestimate experiment by 46 %, while JEFF 3.1 by 9.5 %.

Název v anglickém jazyce

Neutron flux measurement and calculation behind wer-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 InA of monitor current, which corresponds to 0.01 W 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 difference between the theoretical and measured decay. Both neutron and photon transport calculations were performed with the MCNPX 2.6.0 code with different nuclear data libraries. The fast fluxes behind the reactor pressure vessel (RPV) simulator were calculated using fixed source model with defined (calculated by MCNPX) power density across core. The results clearly show the distinguishable dependency of nuclear data libraries on the results. The effect of different libraries is mostly notable in the fluxes over 5 MeV, where the JENDL 4 results overestimate experiment by 46 %, while JEFF 3.1 by 9.5 %.

Druh

D - Stať ve sborníku

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

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Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2015

Kód důvěrnosti údajů

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

Název statě ve sborníku

Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference (M&C+SNA+MC 2015)

ISBN

978-1-5108-0804-1

ISSN

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e-ISSN

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Počet stran výsledku

11

Strana od-do

3102-3112

Název nakladatele

American Nuclear Society ( ANS )

Místo vydání

La Grange Park, IL, USA

Místo konání akce

Nashville, Tennessee, USA

Datum konání akce

19. 4. 2015

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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