Path forward in Gen-IV neutronic experiments at LR-0 reactor

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F17%3AN0000163" target="_blank" >RIV/26722445:_____/17:N0000163 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.euronuclear.org/scientific-resources/conference-proceedings/#" target="_blank" >https://www.euronuclear.org/scientific-resources/conference-proceedings/#</a>

DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Path forward in Gen-IV neutronic experiments at LR-0 reactor

Popis výsledku v původním jazyce

Research at LR-0 reactor is focused on benchmark experiments related to reactors belonging into fourth generation. These experiments are aimed mainly at determination and benchmarking of criticality. Critical benchmarks are then submitted into international database which is operated under auspices of IRPhE (International Reactor Physics Experiment Evaluation) Project of OECD NEA databank. Experimental database broadening helps to validations of codes as well as nuclear data used for design and calculations of GEN-IV reactors. This paper summarizes the past and recent benchmark efforts applied to materials as graphite (Gas Cooled High Temperature Reactor), fluoride salts (Molten Salt Reactor), and lead (Lead Fast Reactor). Performed experiments are modelled in MCNP6.1 code with usage of different nuclear data libraries. Results of criticality measurements are then compared with calculations in form of C/E-1, where possible discrepancies become more apparent. Results show that the benchmark models accurately represent the experiments, where the most of the cases are in 1uncertainty interval. No apparent trend was found in results of calculations among experiments and calculations, but the models of fluorinated compounds are best represented by CENDL- 3.1 data library.

Název v anglickém jazyce

Path forward in Gen-IV neutronic experiments at LR-0 reactor

Popis výsledku anglicky

Research at LR-0 reactor is focused on benchmark experiments related to reactors belonging into fourth generation. These experiments are aimed mainly at determination and benchmarking of criticality. Critical benchmarks are then submitted into international database which is operated under auspices of IRPhE (International Reactor Physics Experiment Evaluation) Project of OECD NEA databank. Experimental database broadening helps to validations of codes as well as nuclear data used for design and calculations of GEN-IV reactors. This paper summarizes the past and recent benchmark efforts applied to materials as graphite (Gas Cooled High Temperature Reactor), fluoride salts (Molten Salt Reactor), and lead (Lead Fast Reactor). Performed experiments are modelled in MCNP6.1 code with usage of different nuclear data libraries. Results of criticality measurements are then compared with calculations in form of C/E-1, where possible discrepancies become more apparent. Results show that the benchmark models accurately represent the experiments, where the most of the cases are in 1uncertainty interval. No apparent trend was found in results of calculations among experiments and calculations, but the models of fluorinated compounds are best represented by CENDL- 3.1 data library.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

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

Rok uplatnění

2017

Kód důvěrnosti údajů

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

Název statě ve sborníku

RRFM 2017 proceedings

ISBN

978-92-95064-28-7

ISSN

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e-ISSN

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Počet stran výsledku

80

Strana od-do

1-8

Název nakladatele

ENS

Místo vydání

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Místo konání akce

Rotterdam, The Netherlands

Datum konání akce

14. 5. 2017

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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