Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F21%3AN0000009" target="_blank" >RIV/26722445:_____/21:N0000009 - isvavai.cz</a>
Result on the web
<a href="https://asmedigitalcollection.asme.org/nuclearengineering/article-abstract/7/2/021402/1096728/Methodology-for-Calculating-Minor-Radioactive?redirectedFrom=fulltext" target="_blank" >https://asmedigitalcollection.asme.org/nuclearengineering/article-abstract/7/2/021402/1096728/Methodology-for-Calculating-Minor-Radioactive?redirectedFrom=fulltext</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1115/1.4049854" target="_blank" >10.1115/1.4049854</a>
Alternative languages
Result language
angličtina
Original language name
Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code
Original language description
After the Fukushima DAIICHI accident, new safety requirements were imposed in order to reduce risk of severe accident. One of the principles that have been adopted is the introduction of emergency action levels resulting from the expected consequences. They cover a wide range of component and system malfunctions resulting in emergency, incident, and/or accident conditions. To evaluate those emergency action levels, thermal hydraulic (TH) analyses simulating these malfunction/incident/accident conditions are required. This paper describes the simulation of a real operational incident scenario using a standard thermal hydraulic model of the power plant in the TRACE code that was originally intended for simulation of design basis accidents such as large break coolant accident or loss of flow accident. Special attention was given to the methodology, addressing a long duration of an incident with corrective actions of the operators, and to computational issues leading to model modifications caused by a long duration of the incident along with the necessary conservatisms in the estimated results of the simulated radioactivity release.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
—
OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
<a href="/en/project/VI20172020085" target="_blank" >VI20172020085: Identification of radiation extraordinary events origin at nuclear power plants and classification system of their relevance</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2021
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Journal of Nuclear Engineering and Radiation Science
ISSN
2332-8983
e-ISSN
2332-8975
Volume of the periodical
7
Issue of the periodical within the volume
2
Country of publishing house
US - UNITED STATES
Number of pages
6
Pages from-to
1-6
UT code for WoS article
000630005800032
EID of the result in the Scopus database
2-s2.0-85103533568