VVER 1000 severe accident analyses using MELCOR code

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F19%3AN0000018" target="_blank" >RIV/26722445:_____/19:N0000018 - isvavai.cz</a>

Výsledek na webu

<a href="https://asmedigitalcollection.asme.org/nuclearengineering/article-abstract/5/3/030913/725908/VVER-1000-Severe-Accident-Analyses-Using-MELCOR?redirectedFrom=fulltext" target="_blank" >https://asmedigitalcollection.asme.org/nuclearengineering/article-abstract/5/3/030913/725908/VVER-1000-Severe-Accident-Analyses-Using-MELCOR?redirectedFrom=fulltext</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1115/1.4043378" target="_blank" >10.1115/1.4043378</a>

Jazyk výsledku

angličtina

Název v původním jazyce

VVER 1000 severe accident analyses using MELCOR code

Popis výsledku v původním jazyce

This work describes the computer model development of the water-water energetic reactor (VVER) 1000 nuclear power plant (NPP) in the methods for estimation of leakages and consequences of releases (MELCOR) 1.8.6 code and its subsequent use for the accident scenarios analysis leading to the core melting. The baseline accident scenario was a stress test case-the station blackout (SBO, the complete loss of alternating current electric power in a nuclear power plant). In addition to this, four other scenarios were analyzed in which the SBO was combined with other technological failures-the loss of steam generator feedwater system and small, medium, and large break coolant accidents (LOCA). The results provided detailed information on the time course of accident scenarios, their temperature and pressure parameters, hydrogen production, and the mass inventory released from the molten corium and debris into the containment of the NPP.

Název v anglickém jazyce

VVER 1000 severe accident analyses using MELCOR code

Popis výsledku anglicky

This work describes the computer model development of the water-water energetic reactor (VVER) 1000 nuclear power plant (NPP) in the methods for estimation of leakages and consequences of releases (MELCOR) 1.8.6 code and its subsequent use for the accident scenarios analysis leading to the core melting. The baseline accident scenario was a stress test case-the station blackout (SBO, the complete loss of alternating current electric power in a nuclear power plant). In addition to this, four other scenarios were analyzed in which the SBO was combined with other technological failures-the loss of steam generator feedwater system and small, medium, and large break coolant accidents (LOCA). The results provided detailed information on the time course of accident scenarios, their temperature and pressure parameters, hydrogen production, and the mass inventory released from the molten corium and debris into the containment of the NPP.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

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

Projekt

<a href="/cs/project/VI20172020076" target="_blank" >VI20172020076: Zpřesnění predikce radiačních následků těžkých havárií jaderných elektráren s cílem identifikace jejich rizik</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)<br>I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2019

Kód důvěrnosti údajů

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

Název periodika

Journal of Nuclear Engineering and Radiation Science

ISSN

2332-8983

e-ISSN

2332-8975

Svazek periodika

5

Číslo periodika v rámci svazku

3

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

9

Strana od-do

1-9

Kód UT WoS článku

000470245100014

EID výsledku v databázi Scopus

2-s2.0-85070822667