Analysis of uncontrolled dilution of boric acid concentration in the reactor VVER-1000/320

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F19%3AN0000010" target="_blank" >RIV/46356088:_____/19:N0000010 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.hanser-elibrary.com/doi/abs/10.3139/124.190015" target="_blank" >https://www.hanser-elibrary.com/doi/abs/10.3139/124.190015</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.3139/124.190015" target="_blank" >10.3139/124.190015</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Analysis of uncontrolled dilution of boric acid concentration in the reactor VVER-1000/320

Popis výsledku v původním jazyce

The paper gives a description of conservative analysis of initiating event associated with uncontrolled dilution of boric acid concentration in the reactor VVER-1000/320 of Temelin NPP. This event is included in the group of beyond design basis accidents. The aim of analysis is to determine also the time interval which is necessary for interventions leading to the deterrence of fuel damage. The failure of operator intervention to isolate dilution routes at intervals shorter than 30 min is assumed. Since the response of the whole NPP system influences the course of safety important parameters of the reactor core, the calculations were made by an externally coupled version of the 3D reactor dynamic code DYN3D and the thermohydraulic system code ATHLET. It is shown that, in addition to exceeding the DNBR limit of more than 99 min from the start of the transient, the remaining safety acceptance criteria will not be violated until the end of the calculation.

Název v anglickém jazyce

Analysis of uncontrolled dilution of boric acid concentration in the reactor VVER-1000/320

Popis výsledku anglicky

The paper gives a description of conservative analysis of initiating event associated with uncontrolled dilution of boric acid concentration in the reactor VVER-1000/320 of Temelin NPP. This event is included in the group of beyond design basis accidents. The aim of analysis is to determine also the time interval which is necessary for interventions leading to the deterrence of fuel damage. The failure of operator intervention to isolate dilution routes at intervals shorter than 30 min is assumed. Since the response of the whole NPP system influences the course of safety important parameters of the reactor core, the calculations were made by an externally coupled version of the 3D reactor dynamic code DYN3D and the thermohydraulic system code ATHLET. It is shown that, in addition to exceeding the DNBR limit of more than 99 min from the start of the transient, the remaining safety acceptance criteria will not be violated until the end of the calculation.

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

—

Návaznosti

N - Vyzkumna aktivita podporovana z neverejnych zdroju

Rok uplatnění

2019

Kód důvěrnosti údajů

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

Název periodika

Kerntechnik

ISSN

0932-3902

e-ISSN

—

Svazek periodika

84

Číslo periodika v rámci svazku

4

Stát vydavatele periodika

DE - Spolková republika Německo

Počet stran výsledku

12

Strana od-do

322-333

Kód UT WoS článku

000493071000016

EID výsledku v databázi Scopus

2-s2.0-85072911909