Nuclear grade concrete behavior under gamma irradiation and loss of coolant accident conditions

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000082" target="_blank" >RIV/26722445:_____/18:N0000082 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Nuclear grade concrete behavior under gamma irradiation and loss of coolant accident conditions

Popis výsledku v původním jazyce

World nuclear power plants NPPs are designed for any case of exceptional state. LOCA, Lost of Coolant Accident is one of the severe accidents. There are three types of LOCA: LOCA inside the reactor when the core melts due to the loosing of the coolant; LOCA inside the containment and LOCA outside the containment vessel. Huge expansion of the temperature and air pressure follows after the loosing of the coolant. It is important to sustain the durability of all the NPP’s components during severe accident as LOCA. Concrete components designed as pre-stressed reinforced concrete wall or reinforced concrete floor of the containment vessel must resist elevated temperatures, steam and air pressure. The in-containment-vessel LOCA will be studied in the article. Its parameters were selected such to be similar to Czech NPP Temelin which has nuclear reactor of WWER 1000. For this experiment the cumulative dose 1.6 to 1.8 ×106 Gy of gamma radiation was applied during 21 + 27 days of irradiation in the gamma irradiator. Then, after non-destructive tests, temperature was rapidly increased onto +250°C and the pressure to +9 bars. It happened during several seconds. Concrete samples were fabricated from the mixed-Portland cement and fine silica aggregates in the laboratory. All were tested non-destructively and after one year they were treated by the high flux gamma radiation. LOCA and post-LOCA conditions followed afterwards in order to simulate the real conditions in NPP. The results showed that the concrete can resist to gamma radiation but during the LOCA condition the material suffer a lot. All studied properties deteriorated after LOCA. The experiment showed the LOCA effect on concrete durability.

Název v anglickém jazyce

Nuclear grade concrete behavior under gamma irradiation and loss of coolant accident conditions

Popis výsledku anglicky

World nuclear power plants NPPs are designed for any case of exceptional state. LOCA, Lost of Coolant Accident is one of the severe accidents. There are three types of LOCA: LOCA inside the reactor when the core melts due to the loosing of the coolant; LOCA inside the containment and LOCA outside the containment vessel. Huge expansion of the temperature and air pressure follows after the loosing of the coolant. It is important to sustain the durability of all the NPP’s components during severe accident as LOCA. Concrete components designed as pre-stressed reinforced concrete wall or reinforced concrete floor of the containment vessel must resist elevated temperatures, steam and air pressure. The in-containment-vessel LOCA will be studied in the article. Its parameters were selected such to be similar to Czech NPP Temelin which has nuclear reactor of WWER 1000. For this experiment the cumulative dose 1.6 to 1.8 ×106 Gy of gamma radiation was applied during 21 + 27 days of irradiation in the gamma irradiator. Then, after non-destructive tests, temperature was rapidly increased onto +250°C and the pressure to +9 bars. It happened during several seconds. Concrete samples were fabricated from the mixed-Portland cement and fine silica aggregates in the laboratory. All were tested non-destructively and after one year they were treated by the high flux gamma radiation. LOCA and post-LOCA conditions followed afterwards in order to simulate the real conditions in NPP. The results showed that the concrete can resist to gamma radiation but during the LOCA condition the material suffer a lot. All studied properties deteriorated after LOCA. The experiment showed the LOCA effect on concrete durability.

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

2018

Kód důvěrnosti údajů

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

Název statě ve sborníku

The 8th International Conference & Workshop REMOO–2018 May 29-31, 2018

ISBN

978-3-9818275-6-9

ISSN

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e-ISSN

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Počet stran výsledku

13

Strana od-do

1-13

Název nakladatele

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Místo vydání

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Místo konání akce

Venice, Italy

Datum konání akce

29. 5. 2018

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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