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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

  • Czech description

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