Uncertainty analysis of rod ejection accident in VVER-1000 reactor

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F19%3A00334551" target="_blank" >RIV/68407700:21220/19:00334551 - isvavai.cz</a>

Alternative codes found

RIV/68407700:21340/19:00334551

Result on the web

<a href="https://doi.org/10.1016/j.anucene.2019.06.061" target="_blank" >https://doi.org/10.1016/j.anucene.2019.06.061</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.anucene.2019.06.061" target="_blank" >10.1016/j.anucene.2019.06.061</a>

Result language

angličtina

Original language name

Uncertainty analysis of rod ejection accident in VVER-1000 reactor

Original language description

In present work the coupling of neutronics code PARCS and thermo-hydraulics code TRACE was performed with adoption of GRS (Gesellschaft fur Anlagen- and Reaktorsicherheit) uncertainty method for rod ejection accident in VVER-1000 reactor core. The determination of input parameters, which represent source of possible uncertainties, for both codes was based on the Phenomenon Identification and Ranking Tables (PIRT) for rod ejection accident in pressurized water reactor (PWR) established by the U.S. Nuclear Regulatory Commission (U.S. NRC). Following input parameters in PARCS were selected: delayed neutron fraction precursor groups, macroscopic cross-section data for density of moderator, temperature of fuel and temperature of moderator. For TRACE code input uncertainty of thermal conductivity of fuel, gap and cladding were defined. The results obtained from uncertainty analyses imply that macroscopic cross-section data of moderator temperature is the most influential uncertainty among the input parameters in a neutronics code. On the other hand, uncertainty of thermal conductivity of uranium fuel significantly affects the results of coupled calculation. The influence of input uncertainties were investigated on the calculated results, mainly for core thermal power, fuel centerline temperature, total reactivity, moderator density, and fuel temperature reactivity.

Czech name

—

Czech description

—

Type

J_imp - Article in a specialist periodical, which is included in the Web of Science database

CEP classification

—

OECD FORD branch

10304 - Nuclear physics

Project

<a href="/en/project/LM2015053" target="_blank" >LM2015053: VR-1 – Training Reactor for Research Activities</a><br>

Continuities

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

Publication year

2019

Confidentiality

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

Name of the periodical

Annals of Nuclear Energy

ISSN

0306-4549

e-ISSN

—

Volume of the periodical

132

Issue of the periodical within the volume

Oct

Country of publishing house

GB - UNITED KINGDOM

Number of pages

8

Pages from-to

628-635

UT code for WoS article

000482247600058

EID of the result in the Scopus database

2-s2.0-85068213786