ANDREA 2.2 and 2.3-Advances in modelling of VVER cores

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F17%3AN0000038" target="_blank" >RIV/46356088:_____/17:N0000038 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.3139/124.110823" target="_blank" >http://dx.doi.org/10.3139/124.110823</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.3139/124.110823" target="_blank" >10.3139/124.110823</a>

Jazyk výsledku

angličtina

Název v původním jazyce

ANDREA 2.2 and 2.3-Advances in modelling of VVER cores

Popis výsledku v původním jazyce

In 2016 a new version of code ANDREA for core design and reload safety analysis of VVER reactors has been released. The new code version includes several major improvements. The first of them is a seamless incorporation of short time kinetics calculations (without temperature feedback) into the code. This new feature accompanied by the possibility of ex-core detector signal predictions enables precise interpretation of dynamic measurements of control assembly weight during the reactor startup. Second important enhancement resides in new flexible format of cross section libraries and in new fuel temperature model based on results of TRANSURANUS fuel performance code. The new code version has been thoroughly tested and validated for both VVER440 and VVER-1000 reactors. Furthermore for the new version 2.3 which is to be released shortly we have implemented the possibility of fluent control assemblies' motion and of non-equidistant axial nodalization schemes in VVER-440 calculations.

Název v anglickém jazyce

ANDREA 2.2 and 2.3-Advances in modelling of VVER cores

Popis výsledku anglicky

In 2016 a new version of code ANDREA for core design and reload safety analysis of VVER reactors has been released. The new code version includes several major improvements. The first of them is a seamless incorporation of short time kinetics calculations (without temperature feedback) into the code. This new feature accompanied by the possibility of ex-core detector signal predictions enables precise interpretation of dynamic measurements of control assembly weight during the reactor startup. Second important enhancement resides in new flexible format of cross section libraries and in new fuel temperature model based on results of TRANSURANUS fuel performance code. The new code version has been thoroughly tested and validated for both VVER440 and VVER-1000 reactors. Furthermore for the new version 2.3 which is to be released shortly we have implemented the possibility of fluent control assemblies' motion and of non-equidistant axial nodalization schemes in VVER-440 calculations.

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

2017

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

82

Číslo periodika v rámci svazku

4

Stát vydavatele periodika

DE - Spolková republika Německo

Počet stran výsledku

7

Strana od-do

448-454

Kód UT WoS článku

000410523500012

EID výsledku v databázi Scopus

2-s2.0-85029231399